Operational experience using the OSTR flip fuel self-protection program
- 1. Oregon State University Radiation Center, Corvallis, OR (United States)
Description
Recent changes in NRC Physical Security regulations make it highly desirable for a small number of TRIGA research reactor establishments to maintain each of the fuel elements in their reactor core above the self-protection dose rate criterion. OSTR operations personnel have written a computer program (SPOOF) which calculates the exposure rate (in Rhr-1) from an irradiated fuel element at 3 feet in air using the actual operating history of the reactor. The purpose of this current paper is to describe the operational experience gained over the last year and a half while using the SPOOF computer program, and while performing the quarterly dose rate measurements needed to confirm the continuing accuracy of the program, and, most importantly, the self-protection status of the OSTR fuel. The computer program in association with the quarterly dose rate measurements have been accepted by the NRC, and allow the OSTR to take credit for self-protecting FLIP fuel under the current physical security regulations
Files
Additional details
Publishing Information
- Imprint Title
- 8. biennial U.S. TRIGA users' conference. Papers and abstracts
- Imprint Pagination
- 240 p.
- Journal Page Range
- p. 5.9-5.20
- Report number
- INIS-US--09N0101
Conference
- Title
- 8. biennial U.S. TRIGA users' conference
- Dates
- 8-10 Mar 1982
- Place
- Idaho Falls, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40028977
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; COMPUTER CODES; DOSE RATES; FUEL ELEMENTS; PERSONNEL; REACTOR CORES; REGULATIONS; SAFETY; SECURITY; SPENT FUELS; TRIGA TYPE REACTORS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; LAWS; MATERIALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs, 3 figs, 1 tab
- Secondary number(s)
- TOC--14