Published 1997
| Version v1
Journal article
Shielding issues in a plutonium storage facility
Description
This paper summarizes the results of a study that investigates shielding issues in a plutonium storage facility. Monte Carlo calculations are performed with MCNP to quantify neutron and gamma doses as a function of various parameters. This summary discusses some of the qualitative aspects of these calculations; however, details of the modeling and results are not presented because of the sensitive nature of some of the data
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 77
- Journal Page Range
- p. 319-320.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1997 American Nuclear Society (ANS) winter meeting.
- Dates
- 16-20 Nov 1997.
- Place
- Albuquerque, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29021072
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; DESIGN; GAMMA RADIATION; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; PLUTONIUM; RADIOACTIVE WASTE STORAGE; SHIELDING
- Descriptors DEC
- ACTINIDES; ELECTROMAGNETIC RADIATION; ELEMENTS; IONIZING RADIATIONS; MANAGEMENT; METALS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; RADIATIONS; STORAGE; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE STORAGE
Optional Information
- Secondary number(s)
- CONF-971125--.