Published 1982 | Version v1
Report Restricted

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

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Part of:
8. biennial U.S. TRIGA users' conference. Papers and abstracts

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)

Optional Information

Notes
2 refs, 3 figs, 1 tab
Secondary number(s)
TOC--14