Point kernel versus radiation transport for iron deep penetration problems
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5752882
The purpose of this study was to determine the relative merits and adequacy of the QAD-CG and QAD-CGGP point kernel codes for spent fuel shielding problems by comparing gamma dose results with those of several radiation transport codes: DOT IV, MORSE SGC, XSDRNPM-S, and MCNP. An intercomparison of results from the radiation transport codes was of secondary interest. The problem considered was an R-Z spent fuel cask model consisting of a homogenized source region (UO/sub 2/ fuel + basket) surrounded by a 38-cm-thick cast iron body. The total cask height is 530 cm. Photon source strengths for eight different discrete energy lines (0.6 to 2.8 MeV) were specified.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 5752882
- Report Number(s):
- CONF-870601-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 54
- 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
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
ALARA
CALCULATION METHODS
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
IONIZING RADIATIONS
KERNELS
POINT KERNELS
RADIATION TRANSPORT
RADIATIONS
SHIELDING
SPENT FUEL STORAGE
STORAGE
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
ALARA
CALCULATION METHODS
ELECTROMAGNETIC RADIATION
GAMMA RADIATION
IONIZING RADIATIONS
KERNELS
POINT KERNELS
RADIATION TRANSPORT
RADIATIONS
SHIELDING
SPENT FUEL STORAGE
STORAGE