This meeting intentionally occurs halfway between the International Conference on Nuclear Criticality (ICNC) editions to encourage and foster the collaboration and connections that occur at ICNC. Bas...
The Working Party on Nuclear Criticality Safety (WPNCS) deals with technical and scientific issues relevant to criticality safety. Specific areas of interest include (but are not limited to) investig...
The NEA nuclear science programme is developed and executed by the Nuclear Science Committee (NSC), comprising high-level scientific experts from all NEA member countries.
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...
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.
The NEA Working Party on Nuclear Criticality Safety (WPNCS) held its bi-annual meetings in June 2023
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...
The Technical Review Groups for both projects met at the NEA headquarters on 3-7 April 2023.
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...
Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report
Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) – NEA/NSC/DOC(95)03
Criticality Calculations of BWR Spent Fuel in Storage and Transportation, Yoshitaka Naito, Hiroshi Okuno and Yoshihara Ando (JAERI)
Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells
Results and Analysis of MOX Fuels Depletion Calculations
Numerical benchmark for the analysis of small-sample reactivity experiments
JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994
Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport
Criticality Calculations of BWR Spent Fuel in Storage and Transport, Hiroshi OKUNO, Yoshitaka NAITO, Yoshihira ANDO
Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)