A systematic study of cross section library based discrepancies in LWR criticality calculations

INIS

• criticality 100%
• nuclear data collections 100%
• comparative evaluations 50%
• data 50%
• geometry 50%
• monte carlo method 50%
• transport 50%
• burnup 50%
• neutrons 50%
• modifications 25%
• control 25%
• balances 25%
• energy 25%
• water 25%
• fuels 25%
• variations 25%
• reactivity 25%
• reactors 25%
• spectra 25%
• multiplication factors 25%
• cross sections 25%
• origin 25%
• reactor physics 25%
• leakage 25%
• neutron transport 25%
• endf 25%
• data processing 25%
• neutron flux 25%
• energy dependence 25%
• fuel pins 25%
• moderators 25%
• evaluated data 25%
• evaluated nuclear data file 25%

Keyphrases

• Cross Section Library 100%
• Criticality Calculation 100%
• Calculation Code 50%
• Monte Carlo Transport 50%
• Transport Calculation 50%
• JENDL 50%
• Multiplication Factor 25%
• Nuclear Data 25%
• Reactor Physics 25%
• Burnable Absorber 25%
• Uncertainty Sources 25%
• Operating Conditions 25%
• Systematic Method 25%
• Neutron Transport Calculation 25%
• Parameter-free 25%
• Light Water Reactor 25%
• Cross-section Data 25%
• Neutron Flux Distribution 25%
• Fuel pin 25%
• Data Processing System 25%
• MCNP4C 25%
• Reactor Criticality 25%
• Energy Group 25%
• Evaluated Data 25%
• Evaluated nuclear Data File 25%
• High Burnup Fuel 25%
• Neutron Cross Section 25%
• Energy Dependence 25%
• Nuclear Data Processing 25%
• Finite Lattice 25%
• Neutron Balance 25%
• Low Burnup 25%
• Pincell 25%

Physics

• Neutron Radiation 100%
• Monte Carlo 66%
• Transportation 66%
• Neutron Transport 33%
• Neutron Cross Section 33%
• Data Transmission 33%
• Flux (Rate) 33%
• Reactor Physics 33%
• Light Water 33%