Monte Carlo minicell approach for a detailed MOX fuel-pin power profile analysis
Creators
- 1. Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States)
Description
The U.S. Department of Energy (DOE) is pursuing two options to dispose of surplus weapons-grade plutonium (WGPu). One option is to burn the WGPu in a mixed-oxide (MOX) fuel form in light water reactors (LWRs). A significant challenge is to demonstrate that the differences between the WG and reactor-grade (RG) MOX fuel are minimal, and therefore, the commercial MOX experience base is applicable. MOX fuel will be irradiated in the Advanced Test Reactor (ATR) to investigate this assertion. Detailed power distributions throughout the MOX pins are required to determine temperature distributions. The purpose of this work is to develop a new Monte Carlo procedure for accurately determining power distributions in fuel pins located in the ATR reflector. Conventional LWR methods are not appropriate because of the unique ATR geometry
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 77
- Journal Page Range
- p. 156-157.
- 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
- 29020971
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL PINS; M CODES; MIXED OXIDE FUELS; MONTE CARLO METHOD; PLUTONIUM; POWER DISTRIBUTION; RADIOACTIVE WASTE MANAGEMENT
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; COMPUTER CODES; DISTRIBUTION; ELEMENTS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; SPATIAL DISTRIBUTION; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT
Optional Information
- Secondary number(s)
- CONF-971125--.