Published date:
19 August 2009
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
2019 review of the EGHPRL and the status of the HPRL - CEA
Published date:
11 March 2020
2019 review of the HPRL system and IT infrastructure - NEA
Published date:
11 March 2020
Published date:
1 January 1991
Published date:
1 January 1991
Published date:
1 January 1990
Published date:
1 January 1993
NEA/NSC/WPEC/DOC(1995)117
Published date:
1 January 1995
Published date:
1 January 1975
Published date:
19 August 2009
NEA/NSC/DOC(2000)4
Several NEA Nuclear Science Committee (NSC) activities are concerned with the validation of computation methods and codes as applied to nuclear technology. One of the challenges has been and continue...
Published date:
17 March 2000
Published date:
1 January 1975
Published date:
1 January 1975
Published date:
19 August 2009
Published date:
19 August 2009
Published date:
19 August 2009
Published date:
19 August 2009
Published date:
19 August 2009
Published date:
22 October 1999
NEA/NSC/WPEC/DOC(1998)174
Published date:
11 June 1999
Published date:
6 November 2001
NEA/NSC/R(2019)1
The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...
Published date:
18 January 2019
Published date:
1 January 1978
Published date:
1 January 1977
Published date:
1 January 1975
Published date:
16 July 2009
Published date:
1 January 1978
Published date:
1 January 1978
Published date:
1 January 1993
Published date:
1 January 1996
NEA/NSC/WPEC/DOC(2005)367
Published date:
10 April 2005
Published date:
1 January 1991
Published date:
1 January 1978
Published date:
1 January 1993
Published date:
1 January 1993
Published date:
1 January 1982
Published date:
23 January 2013
Published date:
2 June 2015
Published date:
25 July 2017
Published date:
1 January 1975
Published date:
1 January 1997
NEA/NSC/WPEC/DOC(2003)289
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(1999)192
Published date:
23 May 2001
Published date:
1 January 1996
Published date:
1 January 1994
Published date:
1 January 1982
Published date:
1 January 1985
NEA Nuclear Science Committee (NSC) meeting, 23-25 September 2020.
Published date:
9 October 2020
Published date:
1 January 1979
Published date:
1 January 1985
NEA/NSC/WPEC/DOC(2006)380
Published date:
8 July 2008
Published date:
1 January 1981
Published date:
1 January 1988
Published date:
1 January 1994
Published date:
1 January 1975
Published date:
1 January 1993
Published date:
1 January 1975
Published date:
1 January 1988
Published date:
1 January 1984
Published date:
1 January 1984
Published date:
1 January 1990
Published date:
1 January 1995
Published date:
1 January 1996
Published date:
1 January 1993
Published date:
1 January 1981
Published date:
1 January 1978
NEA/NSC/WPEC/DOC(2010)429
Published date:
21 December 2010
NEA/NSC/WPEC/DOC(2003)291
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(2001)247
Published date:
23 May 2001
Published date:
1 January 1978
NEA/NSC/WPEC/DOC(2008)409
Published date:
8 July 2008
Published date:
1 January 1975
Published date:
1 January 1974
Published date:
24 February 2000
Published date:
1 January 1991
NEA/NSC/R(2015)9
Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...
Published date:
5 November 2015
NEA/NSC/DOC(2012)11
The objective of the OECD LWR UAM activity is to establish an internationally accepted benchmark framework to compare, assess and further develop different uncertainty analysis methods associated wit...
Published date:
24 May 2012
Published date:
4 December 2007
Published date:
3 June 2003
Published date:
17 March 2004
Published date:
14 November 2005
Published date:
21 November 2005
Published date:
30 March 2000
Published date:
16 June 2009
Published date:
15 October 1999
Published date:
1 January 1993
Published date:
12 June 2012
Published date:
1 January 1993
NEA/NSC/WPEC/DOC(1998)184
Published date:
14 June 1999
NEA/NSC/WPFC/DOC(2012)17
LACANES – Phase I: Isothermal forced convection case
Published date:
12 June 2012
NEA/NSC/R(2018)1
LACANES – Phase II: Natural Convection
Published date:
4 April 2018
NEA/NSC/DOC(2007)1/1
Particle transport calculations in three-dimensional configurations are becoming prevalent in nuclear applications. This places a premium on determining the accuracy of numerical solutions to practic...
Published date:
23 February 2007
NEA/NSC/DOC(2009)8
Saratoga Springs, New York, 6 May 2009 - Meeting summary
Published date:
11 May 2009
Published date:
30 May 2012
Published date:
16 May 2013
Published date:
7 January 2000
Published date:
1 January 1991
Published date:
1 January 1975
NEA/NSC/WPEC/DOC(2001)243
Published date:
23 May 2001
Published date:
1 January 1991
NEA/NSC/R(2016)2
Numerical benchmark for the analysis of small-sample reactivity experiments
Published date:
9 June 2016
NEA/NEACRP/L(1991)337
Simple PWR Spent Fuel Cell (Problem Specification), Makoto TAKANO (JAERI), Michaele BRADY (ORNL), 1991
Published date:
1 January 1991
NEA/NSC/DOC(1992)10
Isotopic Prediction (Problem Specification). Revised, January 1993 Michaele C. Brady<br>See <a href="/html/science/docs/1996/nsc-doc96-06.pdf">NEA/NSC/DOC(96)6</a>.
Published date:
1 January 1992
NEA/NSC/DOC(1993)22
JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994
Published date:
1 January 1993
NEA/NSC/DOC(1996)6
Isotopic Prediction: Final Report, M.D. DeHart (ORNL), M.C. Brady (SNL), C.V. Parks (ORNL). Publication date June 1996. ORNL-6901
Published date:
1 January 1996
NEA/NSC/DOC(1996)1
JAERI-Research 96-003, M. Takano, H. Okuno, (JAERI), publication date: February 1996
Published date:
1 January 1996
NEA/NSC/DOC(1993)15
Effect of Axial Burnup Profile (Infinite fuel pin array) Makoto Takano (JAERI), Michaele Brady (SNL), Alain Santamarina (CEA), June 1993. See NEA/NSC/DOC(96)1
Published date:
1 January 1993
NEA/NSC/DOC(1998)1
Results - Conceptual PWR Spent Fuel Transportation Cask, A. Nouri
Published date:
1 January 1998
Published date:
9 September 2008
Published date:
20 December 2006
NEA/NSC/DOC(2000)12
Criticality Calculations of BWR Spent Fuel in Storage and Transport, Hiroshi OKUNO, Yoshitaka NAITO, Yoshihira ANDO
Published date:
30 June 2000
NEA/NSC/DOC(1997)11
Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)
Published date:
1 January 1997
NEA/NSC/DOC(1996)4
Criticality Calculations of BWR Spent Fuel in Storage and Transportation, Yoshitaka Naito, Hiroshi Okuno and Yoshihara Ando (JAERI)
Published date:
1 January 1996
NEA/NSC/DOC(2002)2
Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport
Published date:
16 January 2002
NEA/NSC/DOC(2003)3
Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells
Published date:
17 April 2003
Published date:
16 May 2003
NEA/NSC/DOC(2003)4
Results and Analysis of MOX Fuels Depletion Calculations
Published date:
17 April 2003
Published date:
16 May 2003
Burn-up credit is a safety approach that accounts for the reduction in the reactivity of configurations with spent nuclear fuel due to the change in their composition after irradiation.
Published date:
2 June 2022
NEA/NSC/R(2015)1
Impact of Isotopic Inventory Changes due to Control Rod Insertions on Reactivity and the End Effect in PWR UO2 Fuel Assemblies
Published date:
2 June 2015
NEA/NSC/R(2015)6
Nuclide Composition and Neutron Multiplication Factor of a Boiling Water Reactor Spent Fuel Assembly for Burn-up Credit and Criticality Control of Damaged Nuclear Fuel
Published date:
2 October 2015
Published date:
21 February 2012
Published date:
23 February 2016
Published date:
1 January 1992
Published date:
1 January 1994
Published date:
1 January 1975
Published date:
1 January 1980
Published date:
17 March 2000
Published date:
22 October 1999
NEA/NSC/WPEC/DOC(1997)156
Published date:
25 May 2001
NEA/NSC/WPEC/DOC(1998)179
Published date:
11 June 1999
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
15 October 1999
NEA/NSC/WPEC/DOC(1997)165
Published date:
10 June 1999
Published date:
1 January 1993
Published date:
1 January 1985
Published date:
18 June 2001
Published date:
1 January 1993
Published date:
1 January 1975
Published date:
1 January 1993
Published date:
1 January 1978
Published date:
1 January 1978
NEA/NSC/DOC(1996)5
The OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components was set up in November 1995 in response to a request...
Published date:
1 January 1996
Published date:
1 January 1992
Published date:
22 October 1999
Published date:
1 January 1991
NEA/NSC/WPEC/DOC(2010)425
Published date:
17 December 2010
Published date:
1 January 1985
Published date:
12 October 2020
NEA/NSC/R(2019)6
The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...
Published date:
18 November 2021
NEA/NSC/WPEC/DOC(2004)322
Published date:
1 June 2004
NEA/NSC/WPEC/DOC(2006)383
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2007)396
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2008)404
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2009)417
Published date:
29 June 2009
NEA/NSC/WPEC/DOC(2003)290
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(2001)246
Published date:
23 May 2001
NEA/NSC/WPEC/DOC(2006)381
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2006)382
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2007)395
Published date:
8 July 2008
A criticality excursion (also referred to as a criticality accident) is the accidental production of a self-sustaining or divergent chain reaction of fissionable material.
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality safety analysis relates to evaluation approaches in data and computat...
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality experiments are controlled tests using fissile materials, like pluton...
Published date:
24 March 2020
Published date:
1 January 1995
Published date:
1 January 1979
NEA/NSC/WPEC/DOC(2001)233
Published date:
23 May 2001
NEA/NSC/WPEC/DOC(1995)126
Published date:
1 January 1995
NEA/NSC/WPEC/DOC(1995)125
Published date:
1 January 1995
NEA/NSC/WPEC/DOC(1997)169
Published date:
10 June 1999
NEA/NSC/WPEC/DOC(2000)215
Published date:
23 May 2001
Published date:
1 January 1991
Published date:
1 January 1991
NEA/NSC/WPEC/DOC(1996)137
Published date:
1 January 1996
Published date:
1 January 1993
Published date:
1 January 1993
NEA/NSC/WPEC/DOC(1999)195
Published date:
23 May 2001
Published date:
4 January 2012
NEA/NSC/WPEC/DOC(2003)280
Published date:
27 June 2003
Published date:
1 January 1993
Published date:
1 January 1975
NEA/NSC/WPEC/DOC(1996)144
Published date:
1 January 1996
Published date:
1 January 1993
DATIF, the DATabase for IFpe, was first developed in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the NE...
Published date:
23 July 2020
Published date:
1 January 1989
Published date:
1 January 1989
Published date:
1 January 1981
NEA/NSC/WPEC/DOC(1995)118
Published date:
1 January 1995
NEA/NSC/WPEC/DOC(2010)426
Published date:
17 December 2010
Published date:
18 March 2009
Published date:
1 January 1979
Published date:
1 January 1978
Published date:
1 January 1978
NEA/NSC/WPEC/DOC(1996)138
Published date:
1 January 1996
Published date:
1 January 1993
NEA/NSC/DOC(1995)3
Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) – NEA/NSC/DOC(95)03
Published date:
24 March 2020
NEA/NSC/WPEC/DOC(2005)357
Published date:
10 April 2005
NEA/NSC/WPEC/DOC(2000)219
Published date:
23 May 2001
NEA/NSC/WPEC/DOC(1995)112
Published date:
1 January 1995
Published date:
1 January 1991
NEA/NSC/WPEC/DOC(1996)148
Published date:
1 January 1996
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
Published date:
11 March 2020
NEA/NSC/WPEC/DOC(1995)130
Published date:
1 January 1995
NEA/NSC/WPEC/DOC(1999)205
Published date:
23 May 2001
Published date:
1 January 1974
Published date:
1 January 1982
Published date:
1 January 1977
Published date:
1 January 1977
Published date:
1 January 1977
Published date:
1 January 1979
Published date:
1 January 1991
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
30 October 2015
Published date:
23 January 2013
Published date:
11 November 2005
NEA/NSC/WPEC/DOC(1995)116
Published date:
1 January 1995
Published date:
20 September 1999
NEA/NSC/WPEC/DOC(1997)172
Published date:
10 June 1999
NEA/NSC/WPEC/DOC(1998)183
Published date:
14 June 1999
NEA/NSC/DOC(1997)18
Tohoku University, Sendai, Japan, 12-13 May 1997
Published date:
1 January 1997
NEA/NSC/WPEC/DOC(2000)217
Published date:
23 May 2001
NEA/NSC/WPEC/DOC(2006)372
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2007)388
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2009)411
Published date:
29 June 2009
NEA/NSC/WPEC/DOC(2008)400
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2004)296
Published date:
1 June 2004
NEA/NSC/WPEC/DOC(2005)335
Published date:
10 April 2005
NEA/NSC/WPEC/DOC(2004)297
Published date:
1 June 2004
NEA/NSC/WPEC/DOC(2005)336
Published date:
10 April 2005
NEA/NSC/WPEC/DOC(2003)274
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(2004)298
Published date:
1 June 2004
NEA/NSC/WPEC/DOC(2004)299
Published date:
1 June 2004
NEA/NSC/WPEC/DOC(2003)271
Published date:
26 June 2003
NEA/NSC/WPEC/DOC(2004)300
Published date:
1 June 2004
NEA/NSC/WPEC/DOC(2003)272
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(2001)231
Published date:
23 May 2001
NEA/NSC/WPEC/DOC(2005)337
Published date:
10 April 2005
NEA/NSC/WPEC/DOC(2002)249
Published date:
1 October 2002
NEA/NSC/WPEC/DOC(2001)229
Published date:
23 May 2001
Published date:
1 January 1978
Published date:
1 January 1975
Published date:
1 January 1976
Published date:
1 January 1988
Published date:
1 January 1978
The expert group primarily acted as a forum for scientific and technical information exchange on advanced light water reactor (LWR) fuels with enhanced accident tolerance.
Published date:
18 October 2022
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Fuel Materials (EGFM) focuses on materials science aspects of...
Published date:
3 March 2023
The expert group works in co-ordination with Working Party on Scientific Issues of Reactor Systems (WPRS) [including the IRPhE Project], Working Party on Scientific Issues of the Fuel Cycle (WPFC) an...
Published date:
9 March 2020
The expert group critically reviewed integral experiments for validating minor actinide (MA) nuclear data, recommended additional integral experiments needed for validating MA nuclear data and invest...
Published date:
5 March 2021
The expert group dealt with the activities associated with the certification of experimental data and benchmark models along with establishing the processes and procedures for using the data and benc...
Published date:
23 November 2021
Published date:
4 February 2008
Under the guidance of the Working Party on Materials Science Issues in Nuclear Fuels and Structural Materials (WPFM), the Expert Group on Structural Materials (EGSM) focuses on materials science aspe...
Published date:
3 March 2023
Published date:
16 June 2006
Published date:
1 January 1978
Published date:
1 January 1978
Published date:
1 January 1976
Published date:
1 January 1975
NEA/NSC/WPEC/DOC(1997)158
Published date:
9 June 1999
Published date:
13 January 2004
Published date:
1 January 1985
NEA/NSC/WPEC/DOC(2005)359
Published date:
10 April 2005
Published date:
1 January 1989
NEA/NSC/WPEC/DOC(2010)427
Published date:
17 December 2010
NEA/NSC/WPEC/DOC(2011)433
Published date:
30 September 2011
NEA/NSC/WPEC/DOC(2010)428
Published date:
17 December 2010
NEA/NSC/WPEC/DOC(2014)446
Published date:
6 January 2014
NEA/NSC/WPEC/DOC(2011)430
Published date:
1 April 2011
NEA/NSC/WPEC/DOC(2013)445
Published date:
4 September 2013
NEA/NSC/WPEC/DOC(2014)447
Published date:
31 March 2014
NEA/NSC/WPEC/DOC(1996)142
Published date:
1 January 1996
Published date:
1 January 1990
Published date:
1 January 1987
NEA/NSC/WPEC/DOC(1995)115
Published date:
1 January 1995
Published date:
9 December 2005
Published date:
1 January 1993
Published date:
1 January 1984
NEA/NSC/WPEC/DOC(2004)325
Published date:
1 June 2004
4 -
6 June 2007
Karlsruhe, Germany
Materials research is a field of growing relevance for innovative nuclear systems, such as Generation IV reactors, critical and sub-critical transmutation systems and fusion devices. For these differ...
Published date:
5 March 2020
Published date:
1 January 1975
NEA/NSC/WPEC/DOC(1995)127
Published date:
1 January 1995
Published date:
1 January 1978
NEA/NSC/WPEC/DOC(2006)385
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(2003)284
Published date:
27 June 2003
Published date:
1 January 1977
Published date:
28 February 2001
Fourth International Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-4) – Programme
Published date:
3 March 2020
14 -
17 October 2019
Antwerp, Belgium
The Nuclear Energy Agency (NEA) organised the fourth international workshop on technology and components of accelerator driven systems (TCADS-4). The meeting was held in Antwerp, Belgium on 14-17 Oct...
Published date:
21 April 2020
Published date:
1 January 1978
Published date:
1 January 1980
Published date:
1 January 1997
Published date:
7 December 2005
As part of the development of advanced nuclear systems, including accelerator-driven systems (ADS) proposed for high-level radioactive waste transmutation and generation IV reactors, heavy liquid met...
Published date:
31 May 2007
Heavy liquid metals such as lead or lead-bismuth have been proposed and investigated as coolants for fast reactors since the 1950s. More recently, there has been renewed interest worldwide in the use...
Published date:
11 August 2015
NEA/NSC/WPEC/DOC(2000)211
Published date:
23 May 2001
Published date:
13 January 2000
Published date:
5 January 2000
Published date:
1 January 1982
NEA/NSC/WPEC/DOC(1996)134
Published date:
1 January 1996
NEA/NSC/WPEC/DOC(1995)131
Published date:
1 January 1995
Published date:
1 January 1993
Published date:
1 January 1986
Published date:
1 January 1976
NEA/NSC/WPEC/DOC(2002)257
Published date:
1 October 2002
Published date:
1 January 1984
Published date:
1 January 1978
NEA/NSC/WPEC/DOC(2007)399
Published date:
8 July 2008
NEA/NSC/R(2020)2
The present report provides a summary of the experiments analysed and consensuses reached by NEA WPEC Subgroup 41, including final recommendations based on all experimental data available at the time...
Published date:
28 September 2020
Published date:
1 January 1977
NEA/NSC/WPEC/DOC(2006)374
Published date:
8 July 2008
NEA/NSC/WPEC/DOC(1995)119
Published date:
1 January 1995
Published date:
1 January 1994
Published date:
16 July 2009
Published date:
1 January 1981
Published date:
1 January 1992
Published date:
1 January 1995
Published date:
2 December 2016
NEA/NSC/R(2015)4
The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...
Published date:
24 June 2015
NEA/NSC/R(2015)7
The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...
Published date:
2 October 2015
Current knowledge of the nuclear physics of fuels and materials provides an understanding and simulation of the operations of nuclear reactors and other systems, both under ordinary and exceptional c...
Published date:
18 July 2019
Published date:
1 January 1994
Published date:
1 January 1983
NEA/NSC/DOC(2013)1
The Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) was created in 2011 to perform specific tasks associated with reactor physics aspects of present and future nuclear power sy...
Published date:
14 January 2013
Published date:
1 January 1988
Published date:
1 January 1987
A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data e...
