EPJ N

Open Access

Thermal decomposition analysis of simulated high-level liquid waste in cold-cap 44

Kota Kawai, Tatsuya Fukuda, Yoshio Nakano and Kenji Takeshita

Published online: 15 December 2016

DOI: https://doi.org/10.1051/epjn/2016038

Open Access

Resonance parameter and covariance evaluation for ¹⁶O up to 6 MeV 43

Luiz Leal, Evgeny Ivanov, Gilles Noguere, Arjan Plompen and Stefan Kopecky

Published online: 24 November 2016

DOI: https://doi.org/10.1051/epjn/2016036

Open Access

The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology 42

Evgenii Bobrov, Pavel Alekseev, Alexander Chibinyaev, Pavel Teplov and Anatoliy Dudnikov

Published online: 28 October 2016

DOI: https://doi.org/10.1051/epjn/2016035

Open Access

Physical and economical aspects of Pu multiple recycling on the basis of REMIX reprocessing technology in thermal reactors 41

Pavel S. Teplov, Pavel N. Alekseev, Evgeniy A. Bobrov and Alexander V. Chibinyaev

Published online: 28 October 2016

DOI: https://doi.org/10.1051/epjn/2016034

Open Access

Evaluation of corrosion on the fuel performance of stainless steel cladding 40

Daniel de Souza Gomes, Alfredo Abe, Antonio Teixeira e Silva, Claudia Giovedi and Marcelo Ramos Martins

Published online: 14 October 2016

DOI: https://doi.org/10.1051/epjn/2016033

Open Access

Initial economic appraisal of nuclear district heating in France 39

Frédéric Jasserand and Jean-Guy Devezeaux de Lavergne

Published online: 27 September 2016

DOI: https://doi.org/10.1051/epjn/2016028

Open Access

Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior 38

José Ordóñez Ródenas, Aurelio Lázaro Chueca and Sebastián Martorell Alsina

Published online: 23 September 2016

DOI: https://doi.org/10.1051/epjn/2016027

Open Access

Multiphysics simulation of fast transients with the FINIX fuel behaviour module 37

Timo Ikonen, Elina Syrjälahti, Ville Valtavirta, Henri Loukusa, Jaakko Leppänen and Ville Tulkki

Published online: 08 September 2016

DOI: https://doi.org/10.1051/epjn/2016032

Open Access

The impact of metrology study sample size on uncertainty in IAEA safeguards calculations 36

Tom Burr, Thomas Krieger, Claude Norman and Ke Zhao

Published online: 16 September 2016

DOI: https://doi.org/10.1051/epjn/2016026

Open Access

Effect of heat transfer correlations on the fuel temperature prediction of SCWRs 35

Erick-Gilberto Espinosa-Martínez, Cecilia Martin-del-Campo, Juan-Luis François and Gilberto Espinosa-Paredes

Published online: 09 September 2016

DOI: https://doi.org/10.1051/epjn/2016030

Open Access

Statistical sampling applied to the radiological characterization of historical waste 34

Biagio Zaffora, Matteo Magistris, Gilbert Saporta and Francesco Paolo La Torre

Published online: 09 September 2016

DOI: https://doi.org/10.1051/epjn/2016031

Open Access

Cross check of the new economic and mass balance features of the fuel cycle scenario code TR_EVOL 33

Iván Merino-Rodríguez, Manuel García-Martínez, Francisco Álvarez-Velarde and Daniel López

Published online: 05 September 2016

DOI: https://doi.org/10.1051/epjn/2016029

Open Access

Measurements of the effective cumulative fission yields of ¹⁴³Nd, ¹⁴⁵Nd, ¹⁴⁶Nd, ¹⁴⁸Nd and ¹⁵⁰Nd for ²³⁵U in the PHENIX fast reactor 32

Edwin Privas, Gilles Noguere, Jean Tommasi, Cyrille De Saint Jean, Karl-Heinz Schmidt and Robert Mills

Published online: 23 August 2016

DOI: https://doi.org/10.1051/epjn/2016025

Open Access

Dose and temperature distribution in spent fuel containing material 31

Ladislav Viererbl, Zdena Lahodová, Jelena Zmítková, Miroslav Vinš and Jiří Šrank

Published online: 17 June 2016

DOI: https://doi.org/10.1051/epjn/2016024

Open Access

Influence of the austenitic stainless steel microstructure on the void swelling under ion irradiation 30

Baptiste Rouxel, Caroline Bisor, Yann De Carlan, Arnaud Courcelle and Alexandre Legris

Published online: 17 June 2016

DOI: https://doi.org/10.1051/epjn/2016023

Open Access

Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors 29

Ross Peel, Luc Van Den Durpel, Mark Daniel Ogden and Karl Rhys Whittle

Published online: 06 June 2016

DOI: https://doi.org/10.1051/epjn/2016022

Open Access

Impact of the thermal scattering law of H in H₂O on the isothermal temperature reactivity coefficients for UOX and MOX fuel lattices in cold operating conditions 28

Juan Pablo Scotta, Gilles Noguere, David Bernard, Jose Ignacio Marquez Damian and Alain Santamarina

Published online: 10 June 2016

DOI: https://doi.org/10.1051/epjn/2016020

Open Access

Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code 27

Claudia Giovedi, Marco Cherubini, Alfredo Abe and Francesco D’Auria

Published online: 31 May 2016

DOI: https://doi.org/10.1051/epjn/2016017

Open Access

Lessons learned from a review of international approaches to spent fuel management 26

David Hambley, Alice Laferrere, W. Steven Walters, Zara Hodgson, Steven Wickham and Phillip Richardson

Published online: 18 May 2016

DOI: https://doi.org/10.1051/epjn/2016019

Open Access

Modelling of powder die compaction for press cycle optimization 25

Jean-Philippe Bayle, Vincent Reynaud, François Gobin, Christophe Brenneis, Eric Tronche, Cécile Ferry and Vincent Royet

Published online: 13 May 2016

DOI: https://doi.org/10.1051/epjn/2016018

Open Access

Testing of high temperature materials within HTR program in Czech Republic 24

Jan Berka and Jana Kalivodová

Published online: 27 April 2016

DOI: https://doi.org/10.1051/epjn/2016021

Open Access

Thermodynamic exergy analysis for small modular reactor in nuclear hybrid energy system 23

Lauren Boldon, Piyush Sabharwall, Cristian Rabiti, Shannon M. Bragg-Sitton and Li Liu

Published online: 27 April 2016

DOI: https://doi.org/10.1051/epjn/2016011

Open Access

2D simulation of hydride blister cracking during a RIA transient with the fuel code ALCYONE 22

Jérôme Sercombe, Thomas Helfer, Eric Federici, David Leboulch, Thomas Le Jolu, Arthur Hellouin de Ménibus and Christian Bernaudat

Published online: 18 April 2016

DOI: https://doi.org/10.1051/epjn/2016016

Open Access

Storage of thermal reactor fuels – Implications for the back end of the fuel cycle in the UK 21

David Hambley

Published online: 15 April 2016

DOI: https://doi.org/10.1051/epjn/2016014

Open Access

Lock-in thermography for characterization of nuclear materials 20

Alexandre Semerok, Sang Pham Tu Quoc, Guy Cheymol, Catherine Gallou, Hicham Maskrot and Gilles Moutiers

Published online: 15 April 2016

DOI: https://doi.org/10.1051/epjn/2016015

Open Access

Modelling of as-fabricated porosity in UO₂ fuel by MFPR code 19

Vladimir I. Tarasov and Mikhail S. Veshchunov

Published online: 15 April 2016

DOI: https://doi.org/10.1051/epjn/2016013

Open Access

Structural integrity assessment and stress measurement of CHASNUPP-1 fuel assembly - Part A: under tensile loading condition 18

Waseem, Ghulam Murtaza, Ashfaq Ahmad Siddiqui and Syed Waseem Akhtar

Published online: 08 April 2016

DOI: https://doi.org/10.1051/epjn/2016008

Open Access

Statistical model of global uranium resources and long-term availability 17

Antoine Monnet, Sophie Gabriel and Jacques Percebois

Published online: 08 April 2016

DOI: https://doi.org/10.1051/epjn/e2016-50058-x

Open Access

Thermalhydraulics of advanced 37-element fuel bundle in crept pressure tubes 16

Joo Hwan Park and Yong Mann Song

Published online: 01 April 2016

DOI: https://doi.org/10.1051/epjn/2016010

Open Access

PWR circuit contamination assessment tool. Use of OSCAR code for engineering studies at EDF 15

Moez Benfarah, Meddy Zouiter, Thomas Jobert, Frédéric Dacquait, Marie Bultot and Jean-Baptiste Genin

Published online: 01 April 2016

DOI: https://doi.org/10.1051/epjn/e2016-50038-4

Open Access

Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes 14

Benjamin A. Lindley, Dan Kotlyar, Geoffrey T. Parks, John N. Lillington and Bojan Petrovic

Published online: 25 March 2016

DOI: https://doi.org/10.1051/epjn/2016012

Open Access

An attempt for a unified description of mechanical testing on Zircaloy-4 cladding subjected to simulated LOCA transient 13

Jean Desquines, Doris Drouan, Elodie Torres, Séverine Guilbert and Pauline Lacote

Published online: 25 March 2016

DOI: https://doi.org/10.1051/epjn/2016009

Open Access

Deployable nuclear fleet based on available quantities of uranium and reactor types – the case of fast reactors started up with enriched uranium 12

Anne Baschwitz, Gilles Mathonnière, Sophie Gabriel and Tommy Eleouet

Published online: 18 March 2016

DOI: https://doi.org/10.1051/epjn/e2016-50073-8

Open Access

Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module 11

Antonella Labarile, Nicolas Olmo, Rafael Miró, Teresa Barrachina and Gumersindo Verdú

Published online: 18 March 2016

DOI: https://doi.org/10.1051/epjn/e2016-50002-7

Open Access

Extraction of uranium from seawater: a few facts 10

Joel Guidez and Sophie Gabriel

Published online: 04 March 2016

DOI: https://doi.org/10.1051/epjn/e2016-50059-2

Open Access

Multiobjective optimization for nuclear fleet evolution scenarios using COSI 9

David Freynet, Christine Coquelet-Pascal, Romain Eschbach, Guillaume Krivtchik and Elsa Merle-Lucotte

Published online: 04 March 2016

DOI: https://doi.org/10.1051/epjn/e2015-50066-7

Open Access

Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor 8

Guifeng Zhu, Yang Zou and Hongjie Xu

Published online: 07 March 2016

DOI: https://doi.org/10.1051/epjn/e2015-50032-6

Open Access

Investigation of the relationships between mechanical properties and microstructure in a Fe-9%Cr ODS steel 7

Benjamin Hary, Thomas Guilbert, Pierre Wident, Thierry Baudin, Roland Logé and Yann de Carlan

Published online: 23 February 2016

DOI: https://doi.org/10.1051/epjn/e2016-50008-7

Open Access

Selection of a tool to decision making for site selection for high level waste 6

Jonni Guiller Madeira, Antônio Carlos M. Alvim, Vivian B. Martins and Nilton A. Monteiro

Published online: 10 February 2016

DOI: https://doi.org/10.1051/epjn/e2015-50039-x

Open Access

Evaluations of Mo-alloy for light water reactor fuel cladding to enhance accident tolerance 5

Bo Cheng, Peter Chou and Young-Jin Kim

Published online: 01 February 2016

DOI: https://doi.org/10.1051/epjn/e2015-50060-7

Open Access

Estimation of the radionuclide inventory in LWR spent fuel assembly structural materials for long-term safety analysis 4

Stefano Caruso

Published online: 15 January 2016

DOI: https://doi.org/10.1051/epjn/e2015-50057-8

Open Access

A study of different cases of VVER reactor core flooding in a large break loss of coolant accident 3

Yury Alekseevich Bezrukov, Vladimir Ivanovitc Schekoldin, Sergey Ivanovich Zaitsev, Andrey Nikolaevich Churkin and Evgeny Aleksandrovich Lisenkov

Published online: 15 January 2016

DOI: https://doi.org/10.1051/epjn/e2015-50005-9

Open Access

Thermal-hydraulics/thermal-mechanics temporal coupling for unprotected loss of flow accidents simulations on a SFR 2

Cyril Patricot, Grzegorz Kepisty, Karim Ammar, Guillaume Campioni and Edouard Hourcade

Published online: 11 January 2016

DOI: https://doi.org/10.1051/epjn/e2015-50036-x

Open Access

Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/LSTF test 7 1

Piotr Mazgaj, Jean-Luc Vacher and Sofia Carnevali

Published online: 11 January 2016

DOI: https://doi.org/10.1051/epjn/e2015-50020-7

EPJ Nuclear Sciences & Technologies

Volume 2 (2016)

Thermal decomposition analysis of simulated high-level liquid waste in cold-cap 44

Resonance parameter and covariance evaluation for 16O up to 6 MeV 43

The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology 42

Physical and economical aspects of Pu multiple recycling on the basis of REMIX reprocessing technology in thermal reactors 41

Evaluation of corrosion on the fuel performance of stainless steel cladding 40

Initial economic appraisal of nuclear district heating in France 39

Pumps modelling of a sodium fast reactor design and analysis of hydrodynamic behavior 38

Multiphysics simulation of fast transients with the FINIX fuel behaviour module 37

The impact of metrology study sample size on uncertainty in IAEA safeguards calculations 36

Effect of heat transfer correlations on the fuel temperature prediction of SCWRs 35

Statistical sampling applied to the radiological characterization of historical waste 34

Cross check of the new economic and mass balance features of the fuel cycle scenario code TR_EVOL 33

Measurements of the effective cumulative fission yields of 143Nd, 145Nd, 146Nd, 148Nd and 150Nd for 235U in the PHENIX fast reactor 32

Dose and temperature distribution in spent fuel containing material 31

Influence of the austenitic stainless steel microstructure on the void swelling under ion irradiation 30

Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors 29

Impact of the thermal scattering law of H in H2O on the isothermal temperature reactivity coefficients for UOX and MOX fuel lattices in cold operating conditions 28

Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code 27

Lessons learned from a review of international approaches to spent fuel management 26

Modelling of powder die compaction for press cycle optimization 25

Testing of high temperature materials within HTR program in Czech Republic 24

Thermodynamic exergy analysis for small modular reactor in nuclear hybrid energy system 23

2D simulation of hydride blister cracking during a RIA transient with the fuel code ALCYONE 22

Storage of thermal reactor fuels – Implications for the back end of the fuel cycle in the UK 21

Lock-in thermography for characterization of nuclear materials 20

Modelling of as-fabricated porosity in UO2 fuel by MFPR code 19

Structural integrity assessment and stress measurement of CHASNUPP-1 fuel assembly - Part A: under tensile loading condition 18

Statistical model of global uranium resources and long-term availability 17

Thermalhydraulics of advanced 37-element fuel bundle in crept pressure tubes 16

PWR circuit contamination assessment tool. Use of OSCAR code for engineering studies at EDF 15

Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes 14

An attempt for a unified description of mechanical testing on Zircaloy-4 cladding subjected to simulated LOCA transient 13

Deployable nuclear fleet based on available quantities of uranium and reactor types – the case of fast reactors started up with enriched uranium 12

Comparison of SERPENT and SCALE methodology for LWRs transport calculations and additionally uncertainty analysis for cross-section perturbation with SAMPLER module 11

Extraction of uranium from seawater: a few facts 10

Multiobjective optimization for nuclear fleet evolution scenarios using COSI 9

Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor 8

Investigation of the relationships between mechanical properties and microstructure in a Fe-9%Cr ODS steel 7

Selection of a tool to decision making for site selection for high level waste 6

Evaluations of Mo-alloy for light water reactor fuel cladding to enhance accident tolerance 5

Estimation of the radionuclide inventory in LWR spent fuel assembly structural materials for long-term safety analysis 4

A study of different cases of VVER reactor core flooding in a large break loss of coolant accident 3

Thermal-hydraulics/thermal-mechanics temporal coupling for unprotected loss of flow accidents simulations on a SFR 2

Comparison of CATHARE results with the experimental results of cold leg intermediate break LOCA obtained during ROSA-2/LSTF test 7 1

Resonance parameter and covariance evaluation for ¹⁶O up to 6 MeV 43

Measurements of the effective cumulative fission yields of ¹⁴³Nd, ¹⁴⁵Nd, ¹⁴⁶Nd, ¹⁴⁸Nd and ¹⁵⁰Nd for ²³⁵U in the PHENIX fast reactor 32

Impact of the thermal scattering law of H in H₂O on the isothermal temperature reactivity coefficients for UOX and MOX fuel lattices in cold operating conditions 28

Modelling of as-fabricated porosity in UO₂ fuel by MFPR code 19