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Validation of SCALE-4 for LWR (Light Water Reactor) Fuel in Transportation and Storage Cask Conditions

Conference ·
OSTI ID:6896829
 [1];  [1];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Battelle Pacific Northwest Laboratory, Richland, WA (United States)
+ Show Author Affiliations

This paper presents the results of criticality calculations performed to validate the recently released SCALE-4 modular code system for light water reactor (LWR) fuel under various conditions typical of transportation and storage casks. The modifications in SCALE-4 include NITAWL-II, an updated version of the NITAWL code that performs resonance self-shielding calculations using the Nordeim Integral Treatment. In order to validate SCALE-4 with the new resonance self-shielding treatment, the CSAS4 control module was used to calculate the effective neutron multiplication factor (keff) via the BONAMI3, NITAWL-II, and KENO V.a4 codes. The cross-section library used was the 27 group ENDF/B-IV library, which has been updated for use with NITAWL-II.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Battelle Pacific Northwest Laboratory, Richland, WA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
6896829
Report Number(s):
CONF-901101-9; ON: DE90012948
Country of Publication:
United States
Language:
English

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Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
990200 -- Mathematics & Computers
BONAMI
BWR TYPE REACTORS
CASKS
COMPUTER CALCULATIONS
COMPUTER CODES
CONTAINERS
CRITICALITY
CSAS4 Control Module
ENERGY SOURCES
Evaluated Nuclear Data File (ENDF)
FUELS
KENO V.a
Light Water Reactor (LWR)
MATERIALS
NITAWL-II
NUCLEAR FUELS
Neutron Flux Traps
Neutron Spectra Shift
Nordeim Integral Treatment
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
S CODES
SCALE-4 Modular Code System
SPENT FUEL CASKS
SPENT FUEL STORAGE
SPENT FUELS
STORAGE
TRANSPORT
WATER COOLED REACTORS
WATER MODERATED REACTORS