Under the guidance of the Nuclear Science Committee (NSC) , the Working Party on Nuclear Criticality Safety (WPNCS) focuses on technical and scientific issues related to criticality safety. Specific...
WPNCS bi-annual event brought together 80 experts from 17 member countries.
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.
Numerical benchmark for the analysis of small-sample reactivity experiments
Simple PWR Spent Fuel Cell (Problem Specification), Makoto TAKANO (JAERI), Michaele BRADY (ORNL), 1991
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>.
JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994
Isotopic Prediction: Final Report, M.D. DeHart (ORNL), M.C. Brady (SNL), C.V. Parks (ORNL). Publication date June 1996. ORNL-6901
JAERI-Research 96-003, M. Takano, H. Okuno, (JAERI), publication date: February 1996
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
Results - Conceptual PWR Spent Fuel Transportation Cask, A. Nouri
Criticality Calculations of BWR Spent Fuel in Storage and Transport, Hiroshi OKUNO, Yoshitaka NAITO, Yoshihira ANDO
Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)
Criticality Calculations of BWR Spent Fuel in Storage and Transportation, Yoshitaka Naito, Hiroshi Okuno and Yoshihara Ando (JAERI)
Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport
Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells
Results and Analysis of MOX Fuels Depletion Calculations