Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

Engineering, Physics, Novice User +15

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

M. B. Chadwick, P. Obložinský, M. Herman et al. · Nuclear Data Sheets · 2006 · 2.2K citations · Full text

Nuclear Data Library, Nuclear Energy, Nuclear Physics +7

INTERNATIONAL REACTOR DOSIMETRY FILE: IRDF-2002

R. Paviotti-Corcuera, V. Zerkin, É. M. Zsolnay et al. · 2003 · 107 citations

Nuclear Engineering, Nuclear Safety, Engineering +1

Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data

A. Vasiliev, H. Ferroukhi, Martin Zimmermann et al. · Annals of Nuclear Energy · 2007 · 32 citations · Full text

Fluence Analysis, Engineering, Nuclear Physics +8

USNRC Draft Regulatory Guide: DG-1053, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence

E.D. McGarry, James Adams · 1996 · 29 citations

Engineering, Nuclear Physics, Nuclear Engineering +9