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AbstractAbstract
[en] The Cycle 8A static tests conducted in the Fast Flux Test Facility (FFTF) during 1986 have resulted in the separation of various feedback reactivity components. These feedback components, described by closed-form equations depending only on the reactor temperature field, can be regarded as database for the validation and/or calibration of feedback mechanistic models. The SASSYS safety analysis code contains the most developed feedback reactivity models and was selected for the comparison study between database and mechanistic calculations for the FFTF. Although detailed feedback models for control rod repositioning and core radial expansion/bowing exist, only the simple models were available in SASSYS at the time of this study. The results are described in this paper
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Apr 1988; 6 p; Safety of next generation power reactors; Seattle, WA (USA); 1-6 May 1988; CONF-880506--25; Available from NTIS, PC A02/MF A01; 1 as DE89000516; Portions of this document are illegible in microfiche products.
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