Point kernel versus radiation transport for iron deep penetration problems
Conference
·
OSTI ID:6466964
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 also 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. 8 refs., 1 tab.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6466964
- Report Number(s):
- CONF-870601-10; ON: DE87005720
- Country of Publication:
- United States
- Language:
- English
Similar Records
Point kernel versus radiation transport for iron deep penetration problems
Homogeneous Versus Heterogeneous Shielding Modeling of Spent-Fuel Casks
Shielding analysis considerations for spent-fuel transport and storage casks
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5752882
Homogeneous Versus Heterogeneous Shielding Modeling of Spent-Fuel Casks
Conference
·
Sun Jun 07 00:00:00 EDT 1992
· Transactions of the American Nuclear Society
·
OSTI ID:7036530
Shielding analysis considerations for spent-fuel transport and storage casks
Conference
·
Tue Oct 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5477552
Related Subjects
053000* -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACTINIDE COMPOUNDS
CHALCOGENIDES
COMPUTER CODES
ELECTROMAGNETIC RADIATION
ELEMENTS
ENERGY RANGE
ENERGY SOURCES
FUELS
GAMMA RADIATION
IONIZING RADIATIONS
IRON
KERNELS
MATERIALS
METALS
MEV RANGE
MEV RANGE 01-10
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
POINT KERNELS
Q CODES
RADIATION TRANSPORT
RADIATIONS
REACTOR MATERIALS
SPENT FUELS
TRANSITION ELEMENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACTINIDE COMPOUNDS
CHALCOGENIDES
COMPUTER CODES
ELECTROMAGNETIC RADIATION
ELEMENTS
ENERGY RANGE
ENERGY SOURCES
FUELS
GAMMA RADIATION
IONIZING RADIATIONS
IRON
KERNELS
MATERIALS
METALS
MEV RANGE
MEV RANGE 01-10
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
POINT KERNELS
Q CODES
RADIATION TRANSPORT
RADIATIONS
REACTOR MATERIALS
SPENT FUELS
TRANSITION ELEMENTS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES