Performance of metal and oxide fuel cores during accidents in large liquid-metal-cooled reactors

Journal Article · Fri Jan 31 23:00:00 EST 1992 · Nuclear Technology; (United States)

OSTI ID:5977605

Royl, P H; Kussmaul, G ^[1]; Cahalan, J E; Wigeland, R A ^[2]; Friedel, G ^[3]; Moreau, J ^[4]; Perks, M ^[5]

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1. Kernforschungszentrum Karlsruhe GmbH (Germany)
2. Argonne National Lab., IL (United States)
3. Interatom, W-5060 Bergisch-Gladbach 1 (DE)
4. Centre d'Etude Nucleaires de Cadarache, 13108 Saint-Paul-lez-Durance (FR)
5. AEA-Technology, Risley, Warrington, Cheshire WA3 6AT (GB)

This paper reports on a cooperative effort among European and U.S. analysts, which is an assessment of the comparative safety performance of metal and oxide fuels during accidents in a 3500-MW (thermal), pool-type, liquid-metal-cooled reactor (LMR) is performed. The study focuses on three accident initiators with failure to scram: the unprotected loss-of-flow (ULOF), the unprotected transient overpower, and the unprotected loss-of-heat-sink (ULOHS). Core designs with a similar power output that have been previously analyzed in Europe under ULOF accident conditions are also included in this comparison. Emphasis is placed on identification of design features that provide passive, self-limiting responses to postulated accident conditions and quantification of relative safety margins. The analyses show that in ULOF and ULOHS sequences, metal-fueled LMRs with pool-type primary systems provide larger temperature margins to coolant boiling than do oxide-fueled reactors of the same design.

• OSTI ID: 5977605
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 97:2; ISSN 0029-5450; ISSN NUTYB
• Country of Publication: United States
• Language: English

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