Published date:
1 January 1980
Published date:
1 January 1975
Published date:
1 January 1994
Published date:
1 January 1992
Published date:
23 February 2016
Published date:
21 February 2012
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
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
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
NEA/NSC/DOC(2003)3
Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells
Published date:
17 April 2003
NEA/NSC/DOC(2002)2
Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport
Published date:
16 January 2002
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(1997)11
Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)
Published date:
1 January 1997
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
Published date:
20 December 2006
Published date:
9 September 2008
NEA/NSC/DOC(1998)1
Results - Conceptual PWR Spent Fuel Transportation Cask, A. Nouri
Published date:
1 January 1998
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(1996)1
JAERI-Research 96-003, M. Takano, H. Okuno, (JAERI), publication date: February 1996
Published date:
1 January 1996
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(1993)22
JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994
Published date:
1 January 1993
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/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/R(2016)2
Numerical benchmark for the analysis of small-sample reactivity experiments
Published date:
9 June 2016
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:
11 September 2023
Published date:
1 January 1991
NEA/NSC/WPEC/DOC(2001)243
Published date:
23 May 2001
Published date:
1 January 1975
Published date:
1 January 1991
Published date:
7 January 2000
Published date:
16 May 2013
Published date:
30 May 2012
NEA/NSC/DOC(2009)8
Saratoga Springs, New York, 6 May 2009 - Meeting summary
Published date:
11 May 2009
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/R(2018)1
LACANES – Phase II: Natural Convection
Published date:
4 April 2018
NEA/NSC/WPFC/DOC(2012)17
LACANES – Phase I: Isothermal forced convection case
Published date:
12 June 2012
NEA/NSC/WPEC/DOC(1998)184
Published date:
14 June 1999
Published date:
1 January 1993
Published date:
12 June 2012
NEA/NSC/R(2022)5
This report presents the results of a benchmark study on innovative fuels for fast reactors using fuel performance codes. Irradiation results were shared among participants of the expert group and co...
Published date:
3 April 2023
Published date:
1 January 1993
Published date:
15 October 1999
Published date:
16 June 2009
Published date:
30 March 2000
Published date:
21 November 2005
Published date:
14 November 2005
Published date:
17 March 2004
Published date:
3 June 2003
Published date:
4 December 2007
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
NEA/NSC/R(2021)5
Since the early 2000s there is an increasing demand from nuclear research, industry, safety and regulation for best-estimate predictions to be provided with their confidence bounds. Consequently, an ...
Published date:
18 April 2023
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
Published date:
1 January 1991
Published date:
24 February 2000
Published date:
1 January 1974
Published date:
1 January 1975
NEA/NSC/WPEC/DOC(2008)409
Published date:
8 July 2008
Published date:
1 January 1978
NEA/NSC/WPEC/DOC(2001)247
Published date:
23 May 2001
NEA/NSC/WPEC/DOC(2003)291
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(2010)429
Published date:
21 December 2010
Published date:
1 January 1978
Published date:
1 January 1981
Published date:
1 January 1993
Published date:
1 January 1996
Published date:
1 January 1995
Published date:
1 January 1990
Published date:
1 January 1984
Published date:
1 January 1984
Published date:
1 January 1988
Published date:
1 January 1975
Published date:
1 January 1993
Published date:
1 January 1975
Published date:
1 January 1994
Published date:
1 January 1988
Published date:
1 January 1981
NEA/NSC/WPEC/DOC(2006)380
Published date:
8 July 2008
Published date:
1 January 1985
Published date:
1 January 1979
NEA Nuclear Science Committee (NSC) meeting, 23-25 September 2020.
Published date:
9 October 2020
Published date:
1 January 1985
Published date:
1 January 1982
Published date:
1 January 1994
Published date:
1 January 1996
NEA/NSC/WPEC/DOC(1999)192
Published date:
23 May 2001
NEA/NSC/WPEC/DOC(2003)289
Published date:
27 June 2003
Published date:
1 January 1997
Published date:
1 January 1975
Published date:
25 July 2017
Published date:
2 June 2015
Published date:
23 January 2013
Published date:
1 January 1982
Published date:
1 January 1993
Published date:
1 January 1993
Published date:
1 January 1978
Published date:
1 January 1991
NEA/NSC/WPEC/DOC(2005)367
Published date:
10 April 2005
Published date:
1 January 1996
Published date:
1 January 1993
Published date:
1 January 1978
Published date:
1 January 1978
Published date:
16 July 2009
Published date:
1 January 1975
Published date:
1 January 1977
Published date:
1 January 1978
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:
6 November 2001
NEA/NSC/WPEC/DOC(1998)174
Published date:
11 June 1999
Published date:
22 October 1999
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:
1 January 1975
Published date:
1 January 1975
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:
19 August 2009
Published date:
1 January 1975
NEA/NSC/WPEC/DOC(1995)117
Published date:
1 January 1995
Published date:
1 January 1993
Published date:
1 January 1990
Published date:
1 January 1991
Published date:
1 January 1991
19 -
23 February 2024
NEA headquarters (46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France), remote access only under exceptional circumstances
Published date:
29 November 2023
2019 review of the HPRL system and IT infrastructure - NEA
Published date:
11 March 2020
2019 review of the EGHPRL and the status of the HPRL - CEA
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
Published date:
19 August 2009
24 -
27 October 2023
NEA Headquarters, Boulogne-Billancourt, France
The NEA is organising the 16th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (16IEMPT) on 24-27 October 2023. The meeting will be held at the NEA offices...
Published date:
23 October 2023