Radioisotope Power System Facility shielding analysis

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:5745650

Lu, A H; Morford, R J

A series of calculations for the Radioisotope Power System Facility have been performed. These analyses have determined the shielding required for storage, testing, and transport of /sup 238/Pu heat source modules using the Monte Carlo code MCNP3B. The source terms and the assumptions used have been verified by comparison of calculated dose rates with measured ones. This paper describes the methodology used for shielding designs and the utilization of available variance reduction techniques to improve the computational efficiency. The new version of MCNP (MCNP3B) with a repeated structure capability was used. It decreased the chance for computer model errors and greatly decreased the model setup time. 2 refs., 3 figs., 2 tabs.

• Research Organization: Westinghouse Hanford Co., Richland, WA (USA)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 5745650
• Report Number(s): WHC-SA-0385; CONF-890408-16; ON: DE89015578
• Resource Relation: Conference: Advances in nuclear engineering computation and radiation shielding, Santa Fe, NM, USA, 9-13 Apr 1989; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

07 ISOTOPES AND RADIATION SOURCES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
RADIOISOTOPE HEAT SOURCES
SHIELDING
COMPUTER CODES
COMPUTERIZED SIMULATION
DOSIMETRY
MONTE CARLO METHOD
PLUTONIUM
RADIOISOTOPE GENERATORS
ACTINIDES
ELEMENTS
HEAT SOURCES
METALS
SIMULATION
TRANSURANIUM ELEMENTS
NESDPS Office of Nuclear Energy Space and Defense Power Systems
070300* - Isotopic Power Supplies
050700 - Nuclear Fuels- Fuels Production & Properties
050900 - Nuclear Fuels- Transport
Handling
& Storage