Other publications from Applied Nuclear Physics

Applied nuclear physics in the Alva Myrdal Centre for nuclear disarmament: Non-proliferation and safeguards activities

Grape, Sophie; Andersson, Peter; Branger, Erik; Gustavsson, Cecilia et al.

2023.

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Applied Nuclear Physics in the Alva Myrdal Centre for Nuclear Disarmament: Non-Proliferation and Safeguards Activities

Grape, Sophie

2023.

Assessments of design and operational parameter sensitivity towards plutonium production in heavy water reactors

Gustavsson, Cecilia; Branger, Erik; Fredriksson, Stina; Hallander, Axel et al.

Part of AMC Annual conference 2023, 14-15 June, 2023, 2023, 2023.

Assessments of radiation emission from molten salt reactor spent fuel: Implications for future nuclear safeguards verification

Mishra, Vaibhav; Branger, Erik; Grape, Sophie; Preston, Markus et al.

2023.

Comparison of the physical and operational parameters of the CANDU reactor and the NRX reactor

Gustavsson, Cecilia; Branger, Erik; Grape, Sophie; Mishra, Vaibhav et al.

Part of AMC Annual conference 2023, 14-15 June, 2023, 2023, 2023.

Experimental verification of simulated predictions from the DDSI instrument

Grape, Sophie; Branger, Erik; Elter, Zsolt

Part of Proceedings of the INMM & ESARDA Joint Annual Meeting, May 22-26, 2023, p. 1-10, 2023.

Image analysis to support DCVD verification

Branger, Erik; Grape, Sophie; Preston, Markus

Part of Proceedings of the INMM & ESARDA Joint Annual Meeting, May 22-26, 2023, 2023.

Inverse Uncertainty Quantification for Fuel Performance Modeling

Licentiate Thesis Robertson, Gustav

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Nuclear Data Uncertainty Quantificationfor Reactor Physics Parameters inFluorine-19-based Molten Salt Reactors

Stjärnholm, Sigfrid; Elter, Zsolt; Sjöstrand, Henrik

2023.

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Possibilities for monitoring the composition of an iPWR core using ex-core neutron detectors

Preston, Markus; Branger, Erik; Grape, Sophie; Khotiaintseva, Olena et al.

Part of Proceedings of the INMM & ESARDA Joint Annual Meeting, 2023.

Propagation of F-19 Uncertainties in Molten Salt Reactors

Stjärnholm, Sigfrid; Elter, Zsolt; Sjöstrand, Henrik

2023.

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Retrieving information about the Ågesta reactor in Sweden

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia

Part of AMC Annual conference 2023, 14-15 June, 2023, 2023.

Serpent modelling of pressurized heavy water CANDU reactors

Gustavsson, Cecilia; Andersson, Peter; Branger, Erik; Grape, Sophie et al.

2023.

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Gomez L, Ana Maria

Simulations And Experiments Of Plasma-Induced Effects In Silicon Detectors

2023.

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Spent nuclear fuel analysis for improved safety

Solans, Virginie

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A TALYS based evaluation system for the fast energy range: application to Fe56

Sjöstrand, Henrik; Göök, Alf

2022.

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A technical view on Pakistan's nuclear weapons programme

Gustavsson, Cecilia; Andersson, Peter; Branger, Erik; Grape, Sophie et al.

Part of The first annual conference of the Alva Myrdal Centre for Nuclear Disarmament, 19-22 October 2022, Uppsala, 2022.

Addressing Model Inadequacy in Inverse Uncertainty Quantification for Fuel Performance Modeling by using a Hierarchical Statistical Formulation

Robertson, Gustav; Sjöstrand, Henrik; Andersson, Peter

Part of SIAM 2022, p. 6-6, 2022.

Att tillverka ett kärnvapen - Hur svårt är det?

Andersson, Peter

2022.

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Gao, Zhihao

Benchmark of simulation of an ion guide for neutron-induced fission products

2022.

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Coincidence spectroscopy for increased sensitivity in radionuclide monitoring

Andersson, Peter; Göök, Alf; Rathore, Vikram; Andersson Sundén, Erik et al.

2022.

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Development of a PhD course in verification of nuclear test explosions under AMC

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia; Österlund, Michael et al.

2022.

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Effects of modelling assumptions on Cherenkov light intensity predictions

Branger, Erik; Grape, Sophie; Preston, Markus

2022.

Neptunium: time for nuclear safeguards?

Preston, Markus; Branger, Erik; Grape, Sophie; Mishra, Vaibhav

2022.

Neutron time-of-flight spectrometry of fusion plasmas at JET

data acquisition developments and physics results Eriksson, Benjamin

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Non-proliferation and safeguards activities within the Alva Myrdal Centre for nuclear disarmament

Grape, Sophie; Andersson, Peter; Branger, Erik; Gustavsson, Cecilia et al.

Part of Proceedings of the Symposium on International Safeguards: Reflecting on the Past and Anticipating the Future, 2022.

OPCW as a Model for a TPNW Structure

Kelley, Robert

2022.

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Overview of initial work on spent-fuel verification at MYRRHA

Preston, Markus; Borella, Alessandro; Rossa, Riccardo; Branger, Erik et al.

Part of Symposium on International Safeguards, 2022.

Prediction of fuel salt composition using fuel data libraries developed for the Molten Salt Demonstration Reactor

Mishra, Vaibhav; Branger, Erik; Grape, Sophie; Elter, Zsolt

p. 1-7 2022.

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Radioxenon measurements at the Shelter Object in the New Safe Confinement at Chernobyl Nuclear Power Plant: Proposed concept and initial investigations

Ringbom, Anders; Aldener, Mattias; Fritioff, Tomas; Kastlander, Johan et al.

2022.

Radioxenon measurements at the Shelter Objectin the new Safe Containment at ChernobylNuclear Power Plant

Ringbom, Anders; Aldener, Mattias; Fritioff, Tomas; Kastlander, Johan et al.

2022.

Research on safeguarding molten salt reactor systems at Uppsala University

Mishra, Vaibhav; Branger, Erik; Grape, Sophie; Elter, Zsolt

2022.

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Rossi-Alpha Distribution Analysis of DDSI Data For Spent Nuclear Fuel Investigation

Solans, Virginie; Grape, Sophie; Sjöstrand, Henrik; Branger, Erik et al.

2022.

State-of-the-Art Report by WG4: Technical nuclear non-proliferation and safeguards

Grape, Sophie

2022.

State-of-the-Art Report: Prepared by Working Group 4: Technical nuclear non-proliferation and safeguards under the Alva Myrdal Centre for nuclear disarmament

Grape, Sophie; Andersson, Peter; Branger, Erik; Fedchenko, Vitaly et al.

2022.

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Studies of naval reactor core properties in light of recent AUKUS developments

Grape, Sophie; Branger, Erik; Gustavsson, Cecilia; Kelley, Robert. E. et al.

2022.

Summary of calculations of radial neutron flux distributions in a KBS-3 type geological repository for spent nuclear fuel

Jansson, Peter

2022.

DOI for Summary of calculations of radial neutron flux distributions in a KBS-3 type geological repository for spent nuclear fuel

Surrogates with gradient prediction for inverse uncertainty quantification in fuel performance modeling

Robertson, Gustav

2022.

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Survey study of prompt fission neutrons data and Monte-Carlo simulations

Pelletier, Augustin

2022.

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A note on detection efficiency with a limited axial field of view of a nuclear fuel assembly

Jansson, Peter

2021.

DOI for A note on detection efficiency with a limited axial field of view of a nuclear fuel assembly

A Python program to evaluate calorimetric measurements of decay heat in spent nuclear fuel assemblies

Jansson, Peter

2021.

Analysis of gamma-ray spectroscopy measurements of BWR nuclear fuel assemblies from SKB-50 set and five PWR fuel assemblies performed at Clab in March 2019

Jansson, Peter

2021.

Application of Neural Networks to Nuclear Safeguards

Mishra, Vaibhav

2021.

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Beräkningsuppgift med dator för studenter i tillämpad reaktorfysik: Kritisk massa för blandning av uranbränsle och vatten

Jansson, Peter

2021.

DOI for Beräkningsuppgift med dator för studenter i tillämpad reaktorfysik: Kritisk massa för blandning av uranbränsle och vatten

CaNel - Calibration of Nuclear fuel performance codes: 6-month seminar

Robertson, Gustav

2021.

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CaNel - Calibration of Nuclear fuel performance codes: A hierarchical Bayesian approach to account for model inadequacy

Robertson, Gustav; Sjöstrand, Henrik; Andersson, Peter; Blair, Paul

2021.

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CaNel - Calibration of Nuclear fuel performance codes: Accounting for model inadequacy using a hierarchical Bayesian approach

Robertson, Gustav

2021.

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CaNel - Calibration of Nuclear fuel performance codes: Addressing model inadequacy in fuel performance modelling

Robertson, Gustav

2021.

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CaNel - Calibration of Nuclear fuel performance codes: Treatment of model inadequacies when calibrating cladding oxidation and hydrogen pick-up

Robertson, Gustav

2021.

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Combining DCVD measurements at different alignments for enhanced partial defect detection performance

Branger, Erik; Elter, Zsolt; Grape, Sophie; Jansson, Peter et al.

Part of Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting August 23-26 & August 30-September 1, 2021, 2021.

Comparison Of Different Supervised Machine Learning Algorithms To Predict PWR Spent Fuel Parameters

Mishra, Vaibhav; Branger, Erik; Elter, Zsolt; Grape, Sophie et al.

2021.

CTBT and SAUNA: Presentation for the Division for Applied Nuclear Physics

Gustavsson, Cecilia; Jansson, Peter

2021.

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Decay heat experiments in Sweden: Presentation at SFCOMPO TRG meeting 2021-07-07

Jansson, Peter

2021.

DOI for Decay heat experiments in Sweden: Presentation at SFCOMPO TRG meeting 2021-07-07

Discriminating Between Irradiated MYRRHA Fuel and Light Water Reactor Fuels Using Gamma Rays and Neutrons

Preston, Markus; Borella, Alessandro; Branger, Erik; Grape, Sophie et al.

Part of Proceedings of the INMM & ESARDA Joint Virtual Annual Meeting August 23-26 & August 30-September 1, 2021, 2021, 2021.

Etik på Civilingenjörsprogrammet i Energisystem

Sjöstrand, Henrik

2021.

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Feasibility study of gamma-ray micro-densitometry for the examination of nuclear fuel swelling

Senis, Lorenzo; Rathore, Vikram; Jansson, Peter; Andersson, Peter et al.

2021.

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Gaussian Processes for treatment of model defects in nuclear data evaluations

Sjöstrand, Henrik

Part of MACHINE LEARNING FOR NUCLEAR DATA, 2021.

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Gaussian Processes for treatment of model defects: The tale of the mysteries of nuclear data evaluation, the peril of model defects, and how the Gaussian Process saves the day

Sjöstrand, Henrik

2021.

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KBP6003 - Decay heat rate estimates using calorimetry on 21 PWR assemblies from the SKB-50 set of fuel assemblies

Jansson, Peter

2021.

KBP6003 – Literature review of detector candidates for spent fuel characterisation

Ros, Linus; Jansson, Peter

2021.

KBP6003 - sammanfattning och projektresultat inför STÖL

Jansson, Peter; Ros, Linus; Bengtsson, Martin; Bäckström, Ulrika

2021.

KBP6003 Comparison of measured and calculated Cs-137 activity in BWR fuel assemblies from the SKB-50 set

Jansson, Peter

2021.

KBP6003 Methodology for Uncertainty Analysis of Calorimetric Measurement with the Temperature Rising Method

Jansson, Peter

2021.

Measuring Cs-137 activity in spent nuclear fuel: Presented in a Fission Diagnostics and Safeguards group meeting

Jansson, Peter

2021.

DOI for Measuring Cs-137 activity in spent nuclear fuel: Presented in a Fission Diagnostics and Safeguards group meeting

Nuclear Safeguards Assessments For Verification Of Regular And Non-Regular Light Water Reactor Fuel

Mishra, Vaibhav

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Practical Considerations Of Non-Destructive Verification Of Calculated Cs-137 Content In Spent Nuclear Fuel

Jansson, Peter; Sjöland, Anders

2021.

Progress on evaluation of Fe 56

Sjöstrand, Henrik

2021.

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Re-evaluation of raw data from 6 PWR fuel assemblies from calorimetric measurements at Clab

Bengtsson, Martin; Jansson, Peter

2021.

Räkneuppgifter till Säkerhetsanalyser inom energisektorn

Jansson, Peter; Lantz, Mattias

Uppsala universitet, 2021.

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Spent fuel characterization research at Uppsala University: Presented at kick-off meeting for IAEA CRP on spent fuel characterisation, 2021-02-16

Jansson, Peter; Andersson, Peter; Grape, Sophie; Sjöstrand, Henrik

2021.

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Spent Nuclear fuel Characterisation and Evolution Until Disposal (SFC): Overview presented at the SNETP 2021 Forum, 2021-02-03

Jansson, Peter

2021.

Status of spent fuel characterization research at Uppsala University: Presented at IAEA CRP meeting on SNF characterisation 2021-06-28

Jansson, Peter; Sjöstrand, Henrik; Grape, Sophie; Andersson, Peter et al.

2021.

DOI for Status of spent fuel characterization research at Uppsala University: Presented at IAEA CRP meeting on SNF characterisation 2021-06-28

SUMMARY OF RECENT INVESTIGATIONS RELATED TO PREDICTIONS OF THE EARLY DIE-AWAY TIME τ FROM THE DDSI INSTRUMENT

Grape, Sophie; Elter, Zsolt; Branger, Erik

Part of Proceedings of the INMM & ESARDA Joint Virtual Annual MeetingAugust 23-26 & August 30-September 1, 2021, 2021.

The golden combination of MCMC and Gaussian processes for calibration

Robertson, Gustav

2021.

The open-source toolbox of the nuclear safeguards data scientist

Mishra, Vaibhav; Elter, Zsolt

2021.

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Using Gaussian Processes for the evaluation of Fe-56

Sjöstrand, Henrik

2021.

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Using Gaussian processes to treat model defects in support of nuclear data evaluation

Sjöstrand, Henrik

2021.

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UU progress and plans in WP4- Task 4.1.2

Sjöstrand, Henrik; Göök, Alf

2021.

Att vara forskare - Presentation för Ekuddenskolan ÅK 2

Andersson, Peter

2020.

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Calorimetry of spent nuclear fuel at Clab - Lessons learned from SKB project KBP6003

Jansson, Peter; Bengtsson, Martin; Bäckström, Ulrika

2020.

CaNel – Calibration of Nuclear fuel performance codes: Machine learning for nuclear safety

Robertson, Gustav

p. 1-10 2020.

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CaNel – Calibration of Nuclear fuel performance codes: Treating model inadequacies, nuisance parameters and unrecognized systematic uncertainties

Robertson, Gustav

p. 1-13 2020.

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CaNel – Calibration of Nuclear fuel performance codes: Treating model inadequacies, nuisance parameters and unrecognized systematic uncertainties

Robertson, Gustav

p. 1-43 2020.

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Fission yield studies using mass measurement techniques: Invited talk

Solders, Andreas; Al-Adili, Ali; Canete, L; Eronen, T et al.

2020.

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Göra el av kärnavfall-En strålande idé?

Sjöstrand, Henrik

2020.

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Interfacing TALYS with a Bayesian treatment of model defects and inconsistent data

Schnabel, Georg

2020.

Kappa factors

Jansson, Peter

2020.

KBP6003 - Methodology for Assessment of Calorimetric Measurement with the Temperature Rising Method

Bengtsson, Martin; Jansson, Peter

2020.

KBP6003 - Radiation flux and dose rate in water outside nuclear fuel

Jansson, Peter

2020.

New evaluation methods addressing model defects and data inconsistency

Sjöstrand, Henrik

2020.

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Presentation at 10th Serpent User Group Meeting titled "Use of Serpent Monte-Carlo code for development of 3D full-scale models and analysis of spent fuel quivers"

Mishra, Vaibhav; Elter, Zsolt; Grape, Sophie; Branger, Erik et al.

2020.

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R&D related to final disposal at Uppsala University: Presentation prepared for the ESARDA Final Disposal WG meeting, Mol Feb 7, 2020

Grape, Sophie; Branger, Erik; Elter, Zsolt; Jansson, Peter et al.

2020.

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Spent Nuclear fuel Characterisation and Evolution Until Disposal (SFC): Overview and status

Jansson, Peter

2020.

Uppsala experience of automatic data retrieval and covariance interpretation

Sjöstrand, Henrik

2020.

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80 years of nuclear fission studies - Shouldn't we be done by now?: Invited presentation at Strålsäkerhetsdagar 2019

Pomp, Stephan

2019.

Analysis of the Prior Nuclear Data Correlation and Its Effect on the Adjustment in Bayesian Inference

Kumar, Dinesh; Sjöstrand, Henrik; Bahauddin Alam, Syed; Palau, Jean-Marc et al.

2019.

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Computational Modeling of Doppler Coefficient For 3D AGR Pin-Cell using the Coupling of Deterministic Method & Matlab

Alam, Syed Bahauddin; Tao, Feng; Kumar, Dinesh; Ridwan, T. et al.

2019.

Enhanced verification of irradiated nuclear fuel using Cherenkov light

Branger, Erik

2019.

EURAD: SFC WP: Spent Fuel Characterisation and Evolution Until Disposal

Jansson, Peter; Schillebeeckx, Peter; Zencker, Uwe; Cobos, Joaquin

2019.

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Evaluation methods addressing model defects and data inconsistency

Sjöstrand, Henrik

2019.

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Gamma Emission Tomography for Nuclear Fuel Diagnostics

Andersson, Peter

2019.

Hur mycket väger ett kilo?

Solders, Andreas

2019.

Inspection of LOCA Test Rod IFA-650.16 Using Gamma Emission Tomography

Andersson, Peter; Holcombe, Scott; Tverberg, Terje

2019.

Integral adjustment of nuclear data libraries: finding unrecognized systematic uncertainties and correlations

Sjöstrand, Henrik; Schnabel, Georg; Rochman, Dimitri

Part of Conference program & Abstract book, p. 212-212, 2019.

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Interfacing TALYS with a Bayesian treatment of model defects and inconsistent data

Schnabel, Georg; Sjöstrand, Henrik; Rochman, Dimitri; J. Koning, Arjan

2019.

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Investigating the gamma and neutron radiation around quivers for verification purposes

Elter, Zsolt; Mishra, Vaibhav; Grape, Sophie; Branger, Erik et al.

2019.

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Isomeric yield ratio measurements at IGISOL/JYFLTRAP for assessing angular momenta of fission fragments: Invited talk, NUSTAR seminar series, GSI

Pomp, Stephan

2019.

Jakten på nya kemiska element - Periodiska systemet 150 år: Populärvetenskaplig föredrag, Kulturnatten 2019, Uppsala

Pomp, Stephan

2019.

Kärnkraft - Vad är det?

Andersson, Peter

2019.

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Learning from Google: About A Computational EXFOR Database for Efficient Data Retrieval and Analysis

Schnabel, Georg

2019.

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Machine learning in nuclear safeguards

Grape, Sophie; Branger, Erik; Elter, Zsolt; Jansson, Peter et al.

2019.

Mixture GLS with examples

Schnabel, Georg

2019.

Model defect treatment for 56Fe

Sjöstrand, Henrik; Schnabel, Georg

2019.

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Outcome and Actions of the 2019 Reflection Group of the European Safeguards Research and Development Association (ESARDA)

Janssens, Willem; Niemeyer, Irmgard; Aregbe, Yetunde; Bonino, Francois et al.

2019.

Project Summary of Ph.D. proposal: Calibration of fuel performance codes – treating modelinadequacies, nuisance parameters and unrecognized systematic uncertainties

Sjöstrand, Henrik

2019.

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Prototype of a pipeline for reproducible nuclear data evaluation

Schnabel, Georg

2019.

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Reflection group 2017-2019 report - ESARDA's relevance for the next decade

Aregbe, Yetunde; Bonino, François; Funk, Pierre; Hildingsson, Lars et al.

2019.

Research within technical safeguard at Uppsala university during 2016-2018

Grape, Sophie; Branger, Erik; Caldeira Balkeståhl, Li; Elter, Zsolt et al.

2019.

The identification and treatment of unrecognized uncertainties and the impact on evaluated uncertainties – SG44

Sjöstrand, Henrik; Schnabel, Georg

2019.

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Treating inconsistent data in integral adjustment using Marginal Likelihood Optimization

Sjöstrand, Henrik; Schnabel, Georg; Rochman, Dimitri; Siefman, Daniel

2019.

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Validation of axial flux profiles and development of a modified axial flux model using gamma scans of IFA-677

Andersson, Peter

2019.

VR contribution to PPPT nuclear data development: Evaluation of neutron cross section data in the fast energy range: ENR-PRD.MAT.IREMEV.7.1-T003

Schnabel, Georg; Sjöstrand, Henrik

2019.

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Yet another computational EXFOR database: User manual

Schnabel, Georg

2019.

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Application of Multivariate Analysis to Gamma and Neutron Signatures from Spent Nuclear Fuel

Caldeira Balkeståhl, Li; Elter, Zsolt; Grape, Sophie; Hellesen, Carl

2018.

Bayesian evaluation method(s) with a treatment of unknown uncertainties

Schnabel, Georg

2018.

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Bayesian statistics with a stochastic linear model and its surprising result

Schnabel, Georg

2018.

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Convergence Studies Using Method Of Characteristics Solver For The Reduced-Moderation Water Reactor Model.

Alam, Syed Bahauddin; Almutairi, B.; Kumar, Dinesh; Goodwin, C. S. et al.

2018.

Lohmann, Svenja

Electronic excitation, luminescence and particle emission: Studying ion-induced phenomena in ToF-MEIS

2018.

Geometry-based Variance Reduction in simulations of Passive Gamma Spectroscopy from Spent Nuclear Fuel

Elter, Zsolt; Caldeira Balkeståhl, Li; Grape, Sophie; Hellesen, Carl

2018.

Improved Cherenkov Light Prediction Model for Enhanced DCVD Performance

Branger, Erik; Grape, Sophie; Jansson, Peter; Jacobsson, Staffan

2018.

Inconsistent data and uncertainties – SG44/46

Sjöstrand, Henrik; Schnabel, Georg

2018.

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Inspection of LOCA Test Rod IFA-650.16 Using Gamma Emission Tomography

Andersson, Peter; Holcombe, Scott; Tverberg, Terje

2018.

International Workshop on Numerical Modelling of NDA Instrumentation and Methods for Nuclear Safeguards: (NM-NDA-IMNS18)

Bourva, Ludovic; Jansson, Peter

2018.

DOI for International Workshop on Numerical Modelling of NDA Instrumentation and Methods for Nuclear Safeguards: (NM-NDA-IMNS18) Download full text (pdf) of International Workshop on Numerical Modelling of NDA Instrumentation and Methods for Nuclear Safeguards: (NM-NDA-IMNS18)

Justified co-variance data by treating model defects; fitting optimized energy-dependent model parameters in Fe-56 nuclear data evaluation

Sjöstrand, Henrik; Helgesson, Petter

2018.

MCNP simulations of prototype DDSI detector

Caldeira Balkeståhl, Li; Elter, Zsolt; Grape, Sophie; Hellesen, Carl

2018.

Model defect treatment for ⁵⁶Fe

Sjöstrand, Henrik; Helgesson, Petter

2018.

Model defect treatment for 56Fe: Model defect treatment for 56Fe Status report: UU contribution to Eurofusion2018: VR contribution to PPPT nuclear data development: Evaluation of neutron cross section data in the fast energy range

Sjöstrand, Henrik; Schnabel, Georg

2018.

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Monte Carlo integral adjustment of nuclear data libraries – experimental covariances and inconsistent data

Sjöstrand, Henrik; Schnabel, Georg; Helgesson, Petter

Part of Book of Abstracts, p. 105-, 2018.

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Nonproliferation and nuclear fuel cycle back-end research at Uppsala University, Sweden: Special Seminar at PNNL

Jansson, Peter

2018.

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Nuclear safeguards verification of modelled BWR fuel using a multivariate analysis approach

Elter, Zsolt; Caldeira Balkeståhl, Li; Grape, Sophie; Hellesen, Carl

2018.

Nuclear safeguards verification of modelled partial defect PWR fuel using multivariate analysis

Caldeira Balkeståhl, Li; Elter, Zsolt; Grape, Sophie; Hellesen, Carl

2018.

Partial defect identification in PWR spent fuel using Passive Gamma Spectroscopy

Elter, Zsolt; Caldeira Balkeståhl, Li; Grape, Sophie; Hellesen, Carl

2018.

Recent ND developments and plans at UU

Schnabel, Georg; Sjöstrand, Henrik

Part of Recent ND developments and plans at UU, 2018.

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The education and training offer in nuclearsafeguards within the EURATOM Research andTraining project “ANNETTE”

Rossa, Riccardo; Niemeyer, Irmgard; Abbas, Kamel; van der Meer, Klaas et al.

2018.

TMC adjustment of nuclear data libraries using integral benchmarks

Sjöstrand, Henrik; Helgesson, Petter; Alhassan, Erwin

2018.

TMC, adjustment to data, and model defects

Helgesson, Petter

2018.

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Treating inconsistent data in Monte Carlo integral adjustment using Marginal Likelihood Optimization

Sjöstrand, Henrik; Schnabel, Georg; Siefman, Daniel

2018.

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Adjustment of nuclear data libraries using integral benchmarks

Sjöstrand, Henrik; Helgesson, Petter; Alhassan, Erwin

2017.

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Analysis of gamma-ray spectroscopy measurements of 25 PWR nuclear fuel assemblies performed at Clab during September and November 2016

Jansson, Peter

2017.

Choosing Nuclear Data evaluation techniques to obtain complete and motivated covariances

Sjöstrand, Henrik; Helgesson, Petter

2017.

Covariance in Ni-59 for JEFF 3.3: A TMC based uncertainty approach

Sjöstrand, Henrik; Helgesson, Petter; Rochman, Dimitri

2017.

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Digital Pulse Processing in HPGe Gamma-ray Spectroscopy: Supplement to the spring 2013, 2016 & 2017 courses on Activity Measurements with Germanium Detectors

Jansson, Peter

Uppsala universitet, 2017.

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Gamma Emission Tomography of LOCA-transient test rods

Andersson, Peter

2017.

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Imaging Techniques for Nuclear Decommissioning and Waste Management: Guest lecture at the 9^th edition of the International Summer School on Nuclear Decommissioning and Waste Management in Ispra (Italy) on Sep 11, 2017

Jansson, Peter

2017.

Improved nuclear data for enhanced nuclear safety

Sjöstrand, Henrik

2017.

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New chromium evaluation for EuroFusion

Sjöstrand, Henrik

2017.

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nIGISOL 2016: Measurement of n-induced fission yields of tin and antimony

Mattera, Andrea

2017.

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Notes on the world energy supply

Andersson, Peter

2017.

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Outcomes of the JNT 1955 Phase I Viability Study of Gamma EmissionTomography for Spent Fuel Verification

Jacobsson Svärd, Staffan; Smith, Eric; White, Timothy A.; Mozin, Vladimir et al.

2017.

Technologies Potentially Useful for Safeguarding Geological Repositories: ASTOR Group Report 2011–2016

Member State Support Programmes Participating in the ASTOR Task, .; Jansson, Peter

2017.

TENDL adjustments using integral benchmarks

Sjöstrand, Henrik; Helgesson, Petter; Alhassan, Erwin

2017.

Treating defects in nuclear reaction models to improve material damage parameters and their uncertainties

Helgesson, Petter; Sjöstrand, Henrik

2017.

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Treating model defects with a Gaussian Process prior for the parameters

Helgesson, Petter; Sjöstrand, Henrik

2017.

Calculation of uncertainties on DD, DT n/γ flux at potential irradiation positions (vertical ports) and KN2 – U3 by TMC code (L11)

Sjöstrand, Henrik

2016.

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Comparing Nuclear Fission Codes: GEF as standalone code vs GEF+TALYS

Mattera, Andrea; Al-Adili, Ali; Lantz, Mattias; Pomp, Stephan et al.

Part of Fission Product Yields Data. Current status and perspectives, 2016.

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Martinik, Tomas

Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel

2016.

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EUROfusion Report, WP JET3, Deliverable L11 (2016): Calculation of uncertainties on DD, DT n/gamma flux at potential irradiation positions (vertical ports) and KN2 – U3 by TMC code [PMP], milestone L11

Sjöstrand, Henrik

2016.

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Evaluation of the Ni-59 cross sections including thermal (n,alpha), (n,p) and complete uncertainty information

Helgesson, Petter; Sjöstrand, Henrik; Rochman, Dimitri; Koning, Arjan J.

2016.

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Fission Product Yields Data Current status and perspectives: Summary report of an IAEA Technical meeting

Dimitriou, Paraskevi; Hambsch, Franz-Josef; Pomp, Stephan

2016.

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Forskning inom teknisk kärnämneskontroll vid Uppsala universitet under 2014–2015

Grape, Sophie; Jacobsson Svärd, Staffan; Jansson, Peter; Hellesen, Carl et al.

2016.

Gamma Emission Tomography Measurements of Fuel Assemblies at the Halden Reactor

Holcombe, Scott; Andersson, Peter

Part of LWR Fuels with Enhanced Safety and Performance Meeting (Top Fuel 2016), p. 1601-1611, 2016.

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Inspection of LOCA Test Rod IFA-650.15 Using Gamma Emission Tomography

Andersson, Peter; Holcombe, Scott; Tverberg, Terje

2016.

Justified and complete gas-production cross sections with uncertainties for Ni-59 and consequences for stainless steel in LWR spectra

Helgesson, Petter; Sjöstrand, Henrik

2016.

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LOCA Transient Tests at HRP

Andersson, Peter

2016.

Rakopoulos, Vasileios

Measurements of Isomeric Yield Ratios of Proton-Induced Fission of natU and natTh at the IGISOL-JYFLTRAP facility

2016.

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NDA Measurement Analysis of Spent Nuclear Fuel Assemblies at the SwedishClab Facility Using the INDEPTH Code

Grogan, B.; Favalli, Andrea; Jansson, Peter; Liljenfeldt, Henrik et al.

2016.

Ni-59 cross section evaluation: covariance focus

Helgesson, Petter; Sjöstrand, Henrik; Rochman, Dimitri; Koning, Arjan J.

2016.

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Nondestructive Assay Data Integration with the SKB-50 Assemblies - FY16 Update

Tobin, Stephen; Fugate, Michael; Trellue, Holly; De-Baere, Paul et al.

2016.

DOI for Nondestructive Assay Data Integration with the SKB-50 Assemblies - FY16 Update

Non-destructive Determination of the Rod-wise Fission Gas Release Fraction Using Gamma Emission Tomography on Complete Fuel Assemblies

Holcombe, Scott; Andersson, Peter; Jacobsson Svärd, Staffan; Hallstadius, Lars

2016.

Novel nuclear data evaluation combining sampling of experimental uncertainty components and TALYS parameters: Applied to helium production due to Ni-59 in stainless steel

Helgesson, Petter; Sjöstrand, Henrik

2016.

INDC(NDS)-0719

Griffin, Peter J.; Sjöstrand, Henrik; Simakov, Stanislav

2016.

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Research into Measured and Simulated Nondestructive Assay Data to Address the Spent Fuel Assay Needs of Nuclear Repositories

Tobin, Stephen; Fugate, Michael; Trellue, Holly; Burr, Tom et al.

2016.

Branger, Erik

Studies of Cherenkov light production in irradiated nuclear fuel assemblies

2016.

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The proposed SPIRE project: Challenge, Scope and Impact

Jansson, Peter

2016.

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A platform for feed-forward and follow-up of students' progression in oral presentation within a study programme

Jansson, Peter; Österlund, Michael; Jacobsson Svärd, Staffan; Grape, Sophie

2015.

Accurate FissiOn data for Nuclear Safety (AlFONS): Final Report

Pomp, Stephan; Lantz, Mattias; Solders, Andreas; Mattera, Andrea et al.

2015.

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Building a Strategy for ESARDA - Education, Training and Knowledge Management

Grape, Sophie; Persson, Karin; Andersson Sundén, Erik

2015.

Determining fast-ion velocity-space distribution functions using velocity-space tomography

Jacobsen, Asger; Salewski, Mirko; Geiger, B.; Stagner, L. et al.

2015.

Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel

Martinik, Tomas; Grape, Sophie; Jansson, Peter; Henzl, Vlad et al.

2015.

DOI for Development of Differential Die-Away Instrument for Characterization of Swedish Spent Nuclear Fuel

Helgesson, Petter

Experimental data and Total Monte Carlo: Towards justified, transparent and complete nuclear data uncertainties

2015.

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Föreläsningar i probabilistisk säkerhetsanalys

Jansson, Peter

2015.

ICRH analysis of high-performance JET hybrid discharges using PION modelling and neutron spectrometry measurements

Mantsinen, Mervi J.; Eriksson, Jacob; Challis, Clive; Frigione, D. et al.

2015.

Image analysis methods for partial defect detection using tomographic images on nuclear fuel assemblies

Davour, Anna; Jacobsson, Staffan Svärd; Grape, Sophie

2015.

Jansson, Kaj

Improving the Neutron Cross-section Standards 238U(n,f) and 6Li(n,a): Measurements and Simulations

2015.

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Improving the prediction model for Cherenkov light generation by irradiated nuclear fuel assemblies in wet storage for enhanced partial-defect verification capability

Branger, Erik; Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan

p. 22-29 2015.

DOI for Improving the prediction model for Cherenkov light generation by irradiated nuclear fuel assemblies in wet storage for enhanced partial-defect verification capability

Monte Carlo simulations of a Universal Gamma-Ray Emission Tomography Device

Jansson, Peter; Andersson, Peter; White, Timothy A.; Mozin, Vladimir

2015.

DOI for Monte Carlo simulations of a Universal Gamma-Ray Emission Tomography Device

Binda, Federico

Neutron emission spectroscopy of fusion plasmas with a NE213 liquid scintillator at JET

2015.

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New 59Ni data including uncertainties and consequences for gas production in steel in LWR spectraNew ⁵⁹Ni data including uncertainties and consequences for gas production in steel in LWR spectra

Helgesson, Petter; Sjöstrand, Henrik; J. Koning, Arjan; Rochman, Dimitri

2015.

Nondestructive Assay Data Integration with the SKB-50 Assemblies - Starting with Passive Gamma and Total Neutron Data

Tobin, Stephen; Fugate, Michael; Trellue, Holly; De-Baere, Paul et al.

2015.

Nuclear Data Uncertainty Quantification for the Nuclear Fuel Cycle Using the TMC Method

Sjöstrand, Henrik; Helgesson, Petter; Alhassan, Erwin; Pomp, Stephan

2015.

Passive Tomography for Spent Fuel Verification: Analysis Framework and Instrument Design Study

White, Timothy A.; Jacobsson Svärd, Staffan; Smith, Eric; Mozin, Vladimir et al.

2015.

DOI for Passive Tomography for Spent Fuel Verification: Analysis Framework and Instrument Design Study

Progress in the development of the neutron fluxmonitoring system of the French GEN-IV SFR:simulations and experimental validations

Jammes, Christian; Verma, Vasudha; Hellesen, Carl; Jacobsson Svärd, Staffan

2015.

Reducing A Priori 239Pu Nuclear Data Uncertainty In The Keff Using A Set Of Criticality Benchmarks With Different Nuclear Data Libraries

Alhassan, Erwin; Sjöstrand, Henrik; Rochman, Dimitri; Helgesson, Petter et al.

2015.

Spent fuel characterization for geological repositories: Presented at the 2015 symposium of the Swedish Centre for Nuclear Technology (SKC) October 9

Jansson, Peter

2015.

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Students’ Approaches to Learning from Other Students’ Oral Presentations

Grape, Sophie; Jansson, Peter; Jacobsson Svärd, Staffan; Österlund, Michael

2015.

To see the invisible: open-ended university thermodynamics labs with infrared cameras

Melander, Emil; Haglund, Jesper; Weiszflog, Matthias; Andersson, Staffan

Part of Proceedings från 5:e Utvecklingskonferensen för Sveriges ingenjörsutbildningar, p. 35-37, 2015.

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Tomographic determination of spent fuel assembly pin-wise burnup and cooling time for detection of anomalies

Jacobsson Svärd, Staffan; Andersson, Peter; Davour, Anna; Grape, Sophie et al.

2015.

DOI for Tomographic determination of spent fuel assembly pin-wise burnup and cooling time for detection of anomalies

Towards Transparent, Reproducible And Justified Nuclear Data Uncertainty Propagation For Lwr Applications

Helgesson, Petter; Sjöstrand, Henrik; J. Koning, Arjan; Rochman, Dimitri et al.

2015.

Underwater Testing of Detectors and Electronics Hardware for Spent Fuel Measurements

Ianakiev, Kiril; Swinhoe, Martyn; Iliev, M.L.; Tobin, Stephen et al.

2015.

DOI for Underwater Testing of Detectors and Electronics Hardware for Spent Fuel Measurements

A poloidal section neutron camera for MAST Upgrade

Sangaroon, Siriyaporn; Weiszflog, Matthias; Cecconello, Marco; Conroy, Sean et al.

Part of Fusion Reactor Diagnostics, p. 129-132, 2014.

DOI for A poloidal section neutron camera for MAST Upgrade

Mattera, Andrea

Characterization of a Neutron Source for Fission Yields Studies

2014.

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Characterization of Spent Nuclear Fuel with a Differential Die-Away Instrument

Martinik, Tomas; Henzl, Vladimir; Grape, Sophie; Jacobsson Svärd, Staffan et al.

2014.

Experimental and Analytical Plans for the Non-destructive Assay System of the Swedish Encapsulation and Repository Facilities

Tobin, Stephen; Liljenfeldt, Henrik; Trellue, Holly; Grape, Sophie et al.

2014.

Experimental Comparison between High Purity Germanium and Scintillator Detectors for Determining Burnup, Cooling Time and Decay Heat of Used Nuclear Fuel

Jansson, Peter; Grape, Sophie; Tobin, Steve; Liljenfeldt, Henrik

2014.

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Gamma Emission Tomography for Characterizing Halden Boiling Water Reactor Fuel Assemblies: Instrumentation, Simulations, and Experimental Demonstration

Holcombe, Scott; Jacobsson Svärd, Staffan; Eitrheim, Knut; Hallstadius, Lars

2014.

Gamma Transport Calculations for Gamma Emission Tomography on Nuclear Fuel within the UGET Project

Jansson, Peter; Jacobsson Svärd, Staffan; Grape, Sophie; Davour, Anna et al.

2014.

Gamma-ray Emission Tomography: Modelling and evaluation of partial-defect testing capabilities

Jacobsson Svärd, Staffan; White, Timothy A.; Smith, Eric; Mozin, Vladimir et al.

2014.

HWR-1133: LOCA Test IFA-650.14, Fission Gas Analysis Based on Nondestructive Gamma Spectroscopy Measurements of Short-lived and Long-lived Fission Products

Holcombe, Scott; Hallstadius, Lars

2014.

Image analysis as a tool for improved use of the Digital Cherenkov Viewing Device for inspection of irradiated PWR fuel assemblies.

Branger, Erik; Wernersson, Erik L. G.; Grape, Sophie; Jacobsson, Staffan Svärd

2014.

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Improved DCVD assessments of irradiated nuclear fuel using image analysis techniques

Branger, Erik; Grape, Sophie; Jacobsson Svärd, Staffan; Wernersson, Erik L. G.

2014.

Ion counting efficiencies at the IGISOL facility

Al-Adili, Ali; Jansson, Kaj; Lantz, Mattias; Solders, Andreas et al.

2014.

Measurement of the energy spectrum from the neutron source planned for IGISOL

Mattera, Andrea; Bedogni, Roberto; Rakopoulos, Vasileios; Lantz, Mattias et al.

Part of Proceedings of the ERINDA Workshop, CERN, Geneva, Switzerland, 1-3 October 2013, CERN-Proceedings-2014-002, p. 39-45, 2014.

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Minority ion cyclotron resonance heating in H-mode in presence of the ITER-like wall in JET

Van Eester, D.; Lerche, E.; Jacquet, P.; Bobkov, V. et al.

Part of 41th EPS Conference on Plasma Physics 2014 (EPS 2014): Europhysics Conference Abstracts, 2014.

Neutron spectrometry measurements of energetic deuterons in ICRF heated plasmas with the ITER-like wall at JET

Eriksson, Jacob; Binda, Federico; Conroy, Sean; Ericsson, Göran et al.

Part of 41th EPS Conference on Plasma Physics 2014 (EPS 2014): Europhysics Conference Abstracts, 2014.

Nuclear data uncertainty propagation for a lead-cooled fast reactor: Combining TMC with criticality benchmarks for improved accuracy

Alhassan, Erwin

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Optimization of a Fuel Self-Sustaining Battery-Type Fast Reactor

Qvist, Staffan

2014.

Svensk elförsörjning i framtiden – en fråga med globala dimensioner: En tvärvetenskaplig rapport från Uppsala universitet

Håkansson, Ane; Davour, Anna; Grape, Sophie; Hellesen, Carl et al.

2014.

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Towards unattended partial-defect verification of irradiated nuclear fuel assemblies using the DCVD

Branger, Erik; Jacobsson Svärd, Staffan; Grape, Sophie; Wernersson, Erik L. G.

2014.

Transient Simulation of Gas Bubble in a Medium Sized Lead Cooled Fast Reactor

Hellesen, Carl; Wolniewicz, Peter; Jansson, Peter; Håkansson, Ane et al.

Part of Proceedings of the International Conference on Physics of Reactors (PHYSOR 2014), 2014.

Velocity-space interrogation regions of neutron spectrometers

Jacobsen, A.S.; Salewski, M.; Eriksson, Jacob; Ericsson, Göran et al.

Part of 41th EPS Conference on Plasma Physics 2014 (EPS 2014): Europhysics Conference Abstracts, 2014.

A laboratory device for developing analysis tools and methods for gamma emission tomography of nuclear fuel

Jansson, Peter; Grape, Sophie; Jacobsson Svärd, Staffan; Håkansson, Ane

2013.

A Non-destructive Gamma-spectroscopy-based Method for Investigating the Radial Origin of Released Fission Gasses from High Burnup Fuel Pellets

Holcombe, Scott; Jacobsson Svärd, Staffan; Eitrheim, Knut; Hallstadius, Lars

2013.

Gamma emission tomography of nuclear fuel: Objectives and status of the IAEA UGET project

Jansson, Peter; Jacobsson Svärd, Staffan; Grape, Sophie

2013.

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High-energy quasi-monoenergetic neutron fields: existing facilities and future needs

Pomp, Stephan; Bartlett, David; Mayer, Sabine; Reitz, Guenther et al.

2013.

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Improved proliferation resistance of fast reactor blankets manufactured from spent nuclear fuel

Hellesen, Carl; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan et al.

2013.

Improving the proliferation resistance of generation IV fast reactor fuel cycles using blankets manufactured from spent nuclear fuel.

Hellesen, Carl; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan et al.

2013.

Modelling the neutron and gamma fluences at KR2

Dzysiuk, Nataliia; Conroy, Sean; Ericsson, Ericsson

2013.

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Nondestructive Assay Options for Spent Fuel Encapsulation

Tobin, Steve; Jansson, Peter

2013.

DOI for Nondestructive Assay Options for Spent Fuel Encapsulation

Proliferation resistances of Generation IV recycling facilities for nuclear fuel

Åberg Lindell, Matilda

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Prototype Development and Field Trials under the Next Generation Safeguards Initiative Spent Fuel Non-Destructive Assay Project

Tobin, Steve; Grape, Sophie; Jansson, Peter

2013.

Recent modelling studies for analysing the partial-defect detection capability of theDigital Cherenkov Viewing Device

Grape, Sophie; Jacobsson Svärd, Staffan; Lindberg, Bo

2013.

Schematic design and safeguards instrumentation of a Gen IV fuel recycling facility.

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

2013.

Students’ approaches to learning from other students’ oral presentations

Grape, Sophie; Jacobsson Svärd, Staffan; Jansson, Peter; Österlund, Michael

2013.

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TRANSP modelling of experimentally measured fast particle redistribution and losses on MAST

Wodniak, Iwona; Cecconello, Marco; Lake, Richard; Jones, Owen et al.

2013.

Update on the Next Generation Safeguards Initiative’s Spent Fuel Project with Emphasis on Differential Die-Away Research

Martinik, Tomas; Tobin, Stephen; Grape, Sophie; Håkansson, Ane et al.

2013.

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A feasibility study of coolant void detection in a lead-cooled fast reactor using fission chambers

Wolniewicz, Peter

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Experimental determination of the shielding properties of 2 types of concrete

Valldor-Blücher, Johan

2012.

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Fuel ion densities and distributions in fusion plasmas

Modeling and analysis for neutron emission spectrometry Eriksson, Jacob

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Neutron emission from a tritium rich fusion plasma: simulations in view of a possible future d-t campaign at JET

Eriksson, Jacob; Hellesen, Carl; Conroy, Sean; Ericsson, Göran

Part of 39th EPS Conference on Plasma Physics 2012 (EPS 2012): Europhysics Conference Abstracts, 2012.

Holcombe, Scott

Nondestructive Fission Gas Measurements by Means of Gamma Spectroscopy and Gamma Tomography

2012.

TRANSP modelling of neutron emissivity on MAST

Wodniak, Iwona; Gorelenkova, Marina; Conroy, Sean; Cecconello, Marco et al.

2012.

Characterization of a NE-213 liquid scintillator for neutron flux measurement at JET

Binda, Federico

2011.

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Determination of Cerenkov light absorption by fuel pond water using a calibration light source

Parcey, Dennis A.; Chen, J. Dennis; Vogt, Chris; Kosierb, Rick et al.

2011.

Development of a Gamma Tomography Measurement System for Characterizing Halden Boiling Water Reactor Fuel

Holcombe, Scott; Eitrheim, Knut; Jacobsson Svärd, Staffan

2011.

Feasibility study of detection of coolant void in metal-cooled fast reactors using changes in the neutron spectrum

Wolniewicz, Peter; Håkansson, Ane; Jacobsson Svärd, Staffan; Jansson, Peter

2011.

Finite Larmor radii effects in fast ion measurements as demonstrated using neutron emission spectrometry of JET plasmas heated with 3rd harmonic ICRF

Eriksson, Jacob; Hellesen, Carl; Andersson Sundén, Erik; Cecconello, Marco et al.

Part of 38th EPS Conference on Plasma Physics 2011 (EPS 2011): Europhysics Conference Abstracts, 2011.

High Count Rate Neutron Detector Installation at JET

Binda, Federico

2011.

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Al-Adili, Ali

Investigation of ²³⁴U(n,f) with a Frisch-grid ionization chamber

2011.

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Andersson, Peter

Optimization of Equipment for Tomographic Measurements of Void Distributions using Fast Neutrons

2011.

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Partial defect verification using the DCVD: a capability evaluation approach

Grape, Sophie; Jacobsson Svärd, Staffan; Sundkvist, Erik; Parcey, Dennis et al.

2011.

Report on the 8th ESARDA course on nuclear safeguards and non-proliferation

Grape, Sophie; Jonter, Thomas

2011.

Bläckberg, Lisa

Surface coatings as xenon diffusion barriers on plastic scintillators: Improving Nuclear-Test-Ban Treaty verification

2011.

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¹⁰Be in ice - four decades, two ice sheets, 15 deep coring sites

Berggren, Ann-Marie; Aldahan, Ala; Possnert, Göran

2010.

A Medley with over ten years of (mostly) light-ion production measurements at The Svedberg Laboratory

Pomp, Stephan; Bevilacqua, Riccardo; Hayashi, M.; Hirayama, S. et al.

Part of EFNUDAT, p. 07013-, 2010.

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Modelling Cherenkov light from irradiated nuclear fuel assemblies using GEANT4

Grape, Sophie; Jacobsson Svärd, Staffan; Lindberg, Bo; Hjalmarsson, Anders

2010.

Neutron induced light-ion production from iron and bismuth at 175 MeV

Bevilacqua, Riccardo

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Neutron tomography for void distribution measurements

Andersson, Peter; Jacobsson Svärd, Staffan; Sjöstrand, Henrik

Part of ENC 2010 Transactions, p. 40-45, 2010.

Safeguards Licensing Aspects of a Future Gen IV Test Facility: A Case Study

Åberg Lindell, Matilda; Grape, Sophie; Håkansson, Ane; Jacobsson Svärd, Staffan

2010.

Six centuries of annually resolved ¹⁰Be in varved lake sediments and its relation to production rates

Berggren, Ann-Marie; Aldahan, Ala; Possnert, Göran; Haltia-Hovi, Eeva et al.

2010.

Statistical grounds for determining the ability to detect partial defects using the Digital Cherenkov Viewing Device (DCVD)

Grape, Sophie

2010.

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Surface and snow pit ¹⁰Be from the NEEM drill site, Greenland

Berggren, Ann-Marie; Aldahan, Ala; Possnert, Göran; Sturevik Storm, Anna

2010.

An upgrade of the SCANDAL facility for neutron scattering measurements at 175 MeV

Andersson, Pernilla

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An upgrade of the SCANDAL facility for neutron scattering measurements at 175 MeV

Andersson, Pernilla; Tesinsky, Milan; Gustavsson, Cecilia; Blomgren, Jan et al.

2009.

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Cross-validation of JET fast deuterium results from TOFOR and NPA

Gatu Johnson, Maria; Cecconello, Marco; Hellesen, Carl; Andersson Sundén, Erik et al.

Part of 36th EPS Conference on Plasma Physics, Sofia, June 29 - July 3, 2009 ECA Vol.33E, p. P-2.151-, 2009.

Diversion path analysis for the Swedish geological repository

Fritzell, Anni; van der Meer, Klaas

2008.

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System aspects on safeguards for the back-end of the Swedish nuclear fuel cycle

Fritzell, Anni

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Verification of completeness of spent nuclear fuel assemblies by means of tomography

Jacobsson Svärd, Staffan; Lundqvist Saleh, Tobias; Håkansson, Ane

Part of International Conference on the Physics of Reactors, 2008.

Alternative Measuring Approaches in Gamma Scanning on Spent Nuclear Fuel

Kvenangen, Karen

2007.

Automatic Gamma Scanning System for Measurement of Residual Heat in Nuclear Fuel

Osifo, Otasowie

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Characterization of Phoswich Scintillation Detectors for the Focal Plane Hodoscope of Magnetic Proton Recoil Spectrometers for Fusion Neutrons

Giacomelli, L; Hellesen, C; Hjalmarsson, A; Sjöstrand, H et al.

2007.

C/S in Final Disposal Processes - Swedish and Finnish Perspectives

Fritzell, Anni; Honkama, Tapani; Karhu, Paula; Okko, Olli et al.

Part of 29th Annual Symposium on Safeguards and Nuclear Materials Management, 2007.

Determining the Fuel's Characteristics as Important as Counting the Number of Elements: A safeguards perspective on the final disposal of spent nuclear fuel

Fritzell, Anni

2007.

Evaluation of Spectral Unfolding for Neutron Spectroscopy

Andersson Sundén, E; Conroy, S; Ericsson, G; Gatu Johnson, M et al.

2007.

Fusion Power Measurements using a Combined Neutron Spectrometer- Camera at JET

Sjöstrand, H; Andersson Sundén, E; Bertalot, L; Conroy, S et al.

2007.

Fusion Power Measurements Using a combined Neutron Spectrometer-Camera System at ITER

Sjöstrand, Henrik; Andersson Sundén, Erik; Conroy, Sean; Ericsson, Göran et al.

2007.

High-efficiency spectrometer for studies of fragment mass distrubutions in neutron-induced fission at intermediate energies (20-200 MeV)

Batenkov, O; Boikov, G; Eismont, V; Majorov, M et al.

Part of Intyernational Conference on Nuclear Data for Science and Technology, Nice, France, April 22-27, 2007, (accepted), 2007.

ICRH of JET and LHD Majority Ions at their Fundamental Cyclotron Frequency

Krasilnikov, A.V; van Eester, D; Lerche, E; Ongena, J et al.

Part of AIP Conference Proceedings 933, p. 43-, 2007.

ICRH of JET and LHD Majority Ions at their Fundamental Cyclotron Frequency

Krasilnikov, A.V; Van Eester, D; Lerche, E; Ongena, J et al.

2007.

Investigation of the Spectroscopic Performance of a Cadmium Telluride Detector Using Pulse Shape Correction and Digital Techniques

Lager, Charlotte

2007.

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Measurements and Analysis of TOFOR Neutron Spectra from RF and NB Heated JET D plasmas

Hellesen, C; Giacomelli, L; Gatu Johnson, M; Hjalmarsson, A et al.

2007.

Neutron Emission Spectroscopy Diagnosis of Fast Ions in RF (3He) Heated Plasmas at JET

Giacomelli, L; Hjalmarsson, A; Hellesen, C; Gatu Johnson, M et al.

2007.

New Measuring Method Developed to Determine Decay Heat in Spent Nuclear Fuel: Thesis indicates possible simplifications for safeguard work

Willman, Christofer

2007.

Prospects for High Resolution Neutron Spectroscopy on High Power Fusion Devices in View of the Recent Diagnostic Developments at JET

Ericsson, G; Andersson Sundén, E; Conroy, S; Gatu Johnson, M et al.

2007.

Recent Experimental Results and Modeling of RF Heating of (3He)-D JET Plasmas: RF as a Tool to Study Transport

Van Eester, D; Lerche, E; Mantica, P; Marinoni, A et al.

2007.

Safeguards Aspects of Recycling Plutonium into MOX Fuel in Light Water Reactors

Lundqvist, Tobias

Part of 29th Annual Symposium on Safeguards and Nuclear Materials Management, 2007.

The 2.5 MeV Neutron Time-of-Flight Spectrometer TOFOR for Experiments at JET

Gatu Johnson, M; Giacomelli, L; Hjalmarsson, A; Källne, J et al.

2007.

The TOFOR Neutron Spectrometer for High-Performance Measurements of D Plasma Fuel Ion Properties

Gatu Johnson, M; Giacomelli, L; Hjalmarsson, A; Weiszflog, M et al.

2007.

Three-body forces in nuclei

Blomgren, J

2007.

TOFOR Performance for D Plasma Neutron Spectroscopy at JET

Gatu Johnsson, M

Tomographic Techniques for Safeguards Measurements of Nuclear Fuel Assemblies

Lundqvist Saleh, Tobias

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Compositional characterization of high-k dielectric material via XPS and ToF-ERDA

Martin, David; Enlund, Johannes; Kappertz, Oliver; Jensen, Jens

2006.

Correlation between divacancy acceptor states in ion implanted n+p Si diodes studied by DLTS

Vines, L.; Monakhov, E.V.; Kuznetsov, A.Y.; Jensen, Jens et al.

2006.

Effects on the Structural and Magnetic Properties of Amorphous Ribbons caused by 4 MeV Cl^2+ ion irradiations

Sanz, R.; Jaafar, M.; Asenjo, A.; Rosa, W.O. et al.

2006.

Fe doping of GaN by ion implantation

Jensen, Jens; Linnarsson, M.; Aggerstam, T.; Lourdudoss, S. et al.

2006.

Magnetic anisotropy changes induced by high energy ion bombardment

Jaafar, M.; Asenjo, A.; Sanz, R.; Jensen, Jens et al.

2006.

Tectonic control and the orbital forcing on the 3 million year sedimentary record from the Central Indian Basi

Nath, Nagender; Aldahan, Ala; Gupta, S; Borole, V et al.

p. 9-8 2006.

TOFOR - a new 2.5 MeV neutron time-of-flight spectrometer to study fusion plasmas at JET

Gatu Johnson, Maria

Part of Nordíc Network for Women in Physics, p. 61-, 2006.

A Monitor for Neutron Flux measurements up to 20 MeV

Hildebrand, Angelica

A new neutron facility for single-event testing

Prokofiev, A.V; Pomp, S; Blomgren, J; Byström, O et al.

Part of IEEE International Reliability Physics Symposium (IRPS2005): San José, California, USA, April 17-21, 2005, (in press), 2005.

A routine preparation method for AMS measurement of I-129 in solid materials

Englund, Edvard; Alfimov, Vasily; Aldahan, Ala; Possnert, Göran

Part of 10th International conference on accelerator mass spectrometry, Berkeley, p. 75-, 2005.

A study of 2-D spatial distribution of D-D and D-T neutron emission in JET Elmy H-mode plasmas with Tritium puff

Bonheure, George; Conroy, Sean; et al, []

Part of Proceedings of the EPS Conference, (Tarragona, Spain 27th June - 1st July 2005), 2005.

Electronic Stopping Powers for Swift Heavy Ions in Compounds

Zhang, Y.; Weber, W.J.; Grove, A.; Jensen, Jens et al.

Part of Presented at he 13th International Conference on Radiation Effects in Insulators (REI-2005),Santa Fe, New Mexico USA, 2005.

Fragmentation and Ionization of C70 and C60 – a comparison

Zettergren, H.; Reinhed, P.; Stochkel, K.; Schmidt, H.T. et al.

Part of Presented at the 24rd International Conference on Photonic, Electronic and Atomic Collisions (ICPEAC 2005), Rosario, Argentina, 2005.

Ion track formation in thin films of amorphous SiO2 using energies below 1 MeV/u

Jensen, Jens; Possnert, Göran; Razpet, Alenka; Skupinski, Marek

Part of Presented at the 6th International Symposium on Swift Heavy Ions in Matter (SHIM-2005) Aschaffenburg, Germany., 2005.

Outgassing Measurements of Insulators and Printed Circuit Boards

Hedlund, E.; Westerberg, L.

Part of 9th European Vacuum Congress (EVC-9), Paris, France, 2005.

Scanning capacitance microscopy of Si implanted with single Au+ ions

Vines, L.; Monakhov, E.; Maknys, K.; Svensson, B.G. et al.

Part of Presented at the 21st Nordic Semiconductor Meeting, Oslo, Norway, 2005.

Scanning probe microscopy of single Au ion impacts in Si

Vines, L.; Monakhov, E.; Maknys, K.; Svensson, B. G. et al.

Part of Presented at the European Material Research Society (E-MRS 2005) Spring meeting, 2005.

Confinement of Charged Fusion Products in Reversed Shear Tokamak Plasmas

Yavorskij, V.; Conroy, Sean; et al, []

Part of IAEA - 20th Fusion Energy Conference, Vilamoura, Portugal, 1st November 2004, 2004.

Confinement of Fast Tritium Beam Ions in Current Hole Plasmas in JET

Yavorskij,, V.; Conroy, Sean; et al, []

Part of EPS Conference on Controlled Fusion and Plasma Physics, London, UK. 28/06/04., 2004.

Experiment on tritium beam evolution in JET plasmas with fishbones and TAE-modes

Sharapov, S.; Conroy, Sean; et al, []

Part of EPS Conference on Controlled Fusion and Plasma Physics, London, UK. 28/06/04., 2004.

First MeV ions losses measurements using activation technique in reversed B experiments at JET.

Bonheure, George; Conroy, Sean; et al, []

Part of Topical Conference on High Temperature Plasma Diagnostics, San Diego California USA. 19/04/04., 2004.

First Results of Minimum Fisher Regularisation as Unfolding Method in JET Neutron Spectrometry

Mlynar, Jan; Conroy, Sean; et al, []

Part of 23rd Symposium on Fusion Technology, Venice, Italy. 20/09/04., 2004.

Inverstigation of low concentration tritium ICRF heating on JET

Lamalle, P U; Conroy, S; Ericsson, G; Tardocchi, M et al.

Part of Europhysics Conference Abstracts Vol. 28G (2004), 2004.

Magnitude of 129I variability in precipitation over Europe

Alfimov, V; Aldahan, Ala; Possnert, Göran

Part of Goldschmidt Conferences 2004, 6-11 June, Copenhagen. Geochimica et Cosmochimica Acta Volume 68, Issue 11, Supplement 1, p. A493-, 2004.

Measurement of the Fusion Power with the MPR Neutron Spectrometer in the TTE and DTE1 Experiments at JET.

Sjöstrand, Henrik; Conroy, Sean; Ericsson, Göran; Gatu Johnson, Maria et al.

Part of 31st EPS Conference on Plasma Physics, 2004.

Neutron Emission from Beam-Injected Fast Tritons in JET Plasmas with Reversed or Monotonic Magnetic Shear.

Gorini, Giuseppe; Källne, Jan; Voitsekhovitch, I; Adams, M et al.

Part of 31st EPS Conference on Plasma Physics, p. 4-, 2004.

Neutron emission spectroscopy of fuel ion rotation and fusion power components demonstrated in the trace tritium experiments at JET

Giacomelli, Luca; Henriksson, Hans; Tardocchi, Marco; Conroy, Sean et al.

Part of 31st EPS conference on Plasma Physics, p. P-5.171, 2004.

Performance of Neutron Measurements during Trace Tritium Experiments on JET

Popovichev,, S.; Conroy, Sean; et al, []

Part of EPS Conference on Controlled Fusion and Plasma Physics, London, UK. 28/06/04, 2004.

pT fusion by RF-heated protons in JET trace tritium discharges.

Santala,, M.; Conroy, Sean; et al, []

Part of EPS Conference on Controlled Fusion and Plasma Physics, London, UK. 28/06/04., 2004.

Quantitative forward modelling of neutron emission to derive transport coefficients of tritium in JET, including error propagation through to transport parameters

Whiteford, D.; Conroy, Sean; et al, []

Part of EPS Conference on Controlled Fusion and Plasma Physics, London, UK. 28/06/04, 2004.

Residual Nuclide Production from Iron, Lead, and Uranium by Neutron-Induced Reactions up to 180 MeV

Michel, R; Glasser, W; Herpers, U; Schuhmacher, H et al.

Part of Proc. Int. Conf. on Nuclear Data for Science and Technology, 2004.

Riverine 129I in the Baltic region

Kekli, Aziz; Aldahan, Ala; Possnert, Göran

Part of Goldschmidt Conferences 2004, 6-11 June , Copenhagen. Geochimica et Cosmochimica Acta Volume 68, Issue 11, Supplement 1,, p. A 492-, 2004.

Technical and scientific aspects of the JET Trace-Tritium experimental campaign

Jones, Tim; Conroy, Sean; Ericsson, Goran; et al, []

2004.

Transport analysis of trace Tritium experiments on JET using TRANSP code and comparison with theory-based transport models.

Voitsekhovitch, Irina; Conroy, Sean; et al, []

Part of EPS Conference on Controlled Fusion and Plasma Physics, London, UK. 28/06/04., 2004.

A PCI time digitizer for the new JET time-of-flight neutron spectrometer

Sousa, Jorge; Conroy, Sean; Ericsson, Goran; Kallne, Jan et al.

Part of 4th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research, 2003.

A PCI transient recorder module for the JET magnetic proton recoil neutron spectrometer

Combo, Alvaro; Conroy, Sean; Kallne, Jan; Weiszflog, Matthias et al.

Part of 4th IAEA Technical Meeting on Control, Data Acquisition and Remote Participation for Fusion Research, 2003.

A transect of 129I in seawater from the North Pole to the Norwegian Sea

Alfimov, V; Aldahan, Ala; Possnert, Göran

Part of Geophysical Research Abstracts, 5,, 2003, p. 05989-, 2003.

Triton burnup studies at JET

Gorini, G; Källne, J; Conroy, S; Ericsson, G et al.

Part of Europhysics Conference Abstracts Vol. 27A (2003), 2003.

Investigation on the possibility to use fork detector for partial defect verification of spent lwr fuel assemblies: Final report on Task JNT A 1071 (BEL, FIN, SWE) of the Member States’ Support Programme to IAEA Safeguards

Tiita, Antero; Saarinen, Johanna; Tarvainen, Matti; Axell, Kåre et al.

2002.

Projected Neutron Spectroscopy Diagnostics of JET Deuterium Plasmas

Gorini, G; Conroy, S; Ericsson, G; Giacomelli, L et al.

Part of ADVANCED DIAGNOSTICS FOR MAGNETIC AND INERTIAL FUSION, 2001.

Projekt EFFEKT: Dosratsvariation

Jansson, Peter; Håkansson, Ane; Bäcklin, Anders

2001.

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Proposed Neutron Emission Spectroscopy Diagnostics of Energetic Deutrons in JET rium Plasmas

Gorini, G; Conroy, Sean; Ericsson, Göran; Giacomelli, Luca et al.

Part of 7th IAEA TCM on Energetic Particles, 2001.

A calculation of backscatter effects in a tomographic equipment

Jansson, Peter

2000.

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Projekt EFFEKT: Dosimeterplacering

Jansson, Peter; Håkansson, Ane

2000.

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A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel

Jacobsson, Staffan; Håkansson, Ane; Andersson, Camilla; Jansson, Peter et al.

1998.

A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel

Jacobsson, Staffan; Håkansson, Ane; Andersson, Camilla; Jansson, Peter et al.

1998.

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Possibilities and Limitations of the Tomographic Method for verification of the Integrity of Spent Nuclear Fuel

Andersson, Camilla

1997.

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Calibration of the TVO spent BWR reference fuel assembly: Final report on the joint Task JNT61 of the Finnish and Swedish Support Propgrammes to IAEA Safeguards

Tarvainen, Matti; Bäcklin, Anders; Håkansson, Ane

1992.