Improvement of evaluation method for initiating-phase energetics based on CABRI-1 in-pile experiments

Journal Article · Wed Apr 01 04:00:00 EST 1992 · Nuclear Technology; (United States)

OSTI ID:5347413

Nonaka, N; Sato, I ^[1]

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1. Power Reactor and Nuclear Fuel Development Corp., O-arai Engineering Center, Fast Breeder Reactor Safety Engineering Section, Safety Engineering Div., 4002 Narita-machi, O-arai, Ibaraki 311-13 (JP)

In this paper an improved method to evaluate key phenomena in the initiating-phase energetics of unprotected loss-of-flow (ULOF) whole-core accidents in liquid-metal fast breeder reactors is presented. Three phenomena, namely, axial fuel expansion, fuel failure, and postfailure fuel motion, have been examined through the CABRI-1 in-pile experiments and analyses with special emphasis on the self-limiting mechanisms of the energetics potential. For the experiment analyses, the SAD3D, PAPAS-2S, and SAD4A computer codes are employed selectively to obtain a detailed investigation of the phenomena and to validate physical models. The improved knowledge obtained through the research efforts in CABRI-1 and relevant safety experiments has been implemented in the revised SAS3D code. This evaluation method, which accounts for the self-limiting mechanisms, has been applied to a reactor analysis of an energetic ULOF sequence. The results of the application study confirm the importance and effectiveness of the method.

• OSTI ID: 5347413
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 98:1; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

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ACCIDENTS
BREEDER REACTORS
CABRI REACTOR
CALCULATION METHODS
COMPUTER CODES
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LIQUID METALS
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METALS
MOTION
P CODES
PLANNING
POOL TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
S CODES
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THERMAL REACTORS
WATER COOLED REACTORS
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