NEA/NSC/R(2022)1
There is significant international interest in the effects of temperature on criticality safety evaluations. Improved access to nuclear data, notably thermal scattering data S(α,β) for hydrogen in ic...
Published date:
2 November 2023
NEA/NSC/R(2022)6
The goal of the Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) Subgroup on Experimental Needs for Criticality Safety Purposes (SG-5) was to highlight the needs of int...
Published date:
15 September 2023
NEA/NSC/R(2021)3
Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...
Published date:
17 February 2023
NEA/NSC/R(2021)1
This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...
Published date:
30 January 2023
NEA/NSC/R(2022)3/CORR
Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...
Published date:
30 November 2022
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/R(2016)2
Numerical benchmark for the analysis of small-sample reactivity experiments
Published date:
9 June 2016
Published date:
23 February 2016
Published date:
30 October 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
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:
21 February 2012
NEA/NSC/WPNCS/DOC(2011)5
Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report
Published date:
6 June 2011
Published date:
9 September 2008
Published date:
20 December 2006
Published date:
16 May 2003
Published date:
16 May 2003
NEA/NSC/DOC(2003)4
Results and Analysis of MOX Fuels Depletion Calculations
Published date:
17 April 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(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(1998)1
Results - Conceptual PWR Spent Fuel Transportation Cask, A. Nouri
Published date:
1 January 1998
NEA/NSC/DOC(1997)11
Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)
Published date:
1 January 1997
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)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(1996)1
JAERI-Research 96-003, M. Takano, H. Okuno, (JAERI), publication date: February 1996
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(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(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