Posttest analysis of the FFTF inherent safety tests

Conference · Thu Jan 01 00:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5624609

Padilla, A Jr; Claybrook, S W

Inherent safety tests were performed during 1986 in the 400-MW (thermal) Fast Flux Test Facility (FFTF) reactor to demonstrate the effectiveness of an inherent shutdown device called the gas expansion module (GEM). The GEM device provided a strong negative reactivity feedback during loss-of-flow conditions by increasing the neutron leakage as a result of an expanding gas bubble. The best-estimate pretest calculations for these tests were performed using the IANUS plant analysis code (Westinghouse Electric Corporation proprietary code) and the MELT/SIEX3 core analysis code. These two codes were also used to perform the required operational safety analyses for the FFTF reactor and plant. Although it was intended to also use the SASSYS systems (core and plant) analysis code, the calibration of the SASSYS code for FFTF core and plant analysis was not completed in time to perform pretest analyses. The purpose of this paper is to present the results of the posttest analysis of the 1986 FFTF inherent safety tests using the SASSYS code.

• Research Organization: Westinghouse Hanford Co., Richland, WA
• OSTI ID: 5624609
• Report Number(s): CONF-870601-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 54; Conference: Annual meeting of the American Nuclear Society, Dallas, TX, USA, 7 Jun 1987
• Country of Publication: United States
• Language: English

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