Radioisotope Power System Facility shielding analysis
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Westinghouse Hanford Co., Richland, WA (USA)
- OSTI Identifier:
- 5745650
- Report Number(s):
- WHC-SA-0385; CONF-890408-16
ON: DE89015578
- DOE Contract Number:
- AC06-87RL10930
- Resource Type:
- Conference
- 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
- Subject:
- 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
Citation Formats
Lu, A H, and Morford, R J. Radioisotope Power System Facility shielding analysis. United States: N. p., 1989.
Web.
Lu, A H, & Morford, R J. Radioisotope Power System Facility shielding analysis. United States.
Lu, A H, and Morford, R J. 1989.
"Radioisotope Power System Facility shielding analysis". United States. https://www.osti.gov/servlets/purl/5745650.
@article{osti_5745650,
title = {Radioisotope Power System Facility shielding analysis},
author = {Lu, A H and Morford, R J},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/5745650},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 1989},
month = {Sun Jan 01 00:00:00 EST 1989}
}