Analysis of the light-water flooding of the HFBR thimble tubes

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7168342

Carew, J F; Aronson, A L; Cokinos, D M; Prince, A; Todosow, M; Tichler, P R; Cheng, L Y; Karol, R C ^[1]

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1. Brookhaven National Lab., Upton, NY (United States)

The fuel elements surrounding the central vertical thimble tubes in the Brookhaven National Laboratory High-Flux Beam Reactor (HFBR) are highly undermoderated, and light-water flooding of these irradiation thimbles results in a positive core reactivity insertion. The light-water contamination of the D{sub 2}O thimble tube coolant is the result of a postulated double-ended guillotine break of a U tube in the experimental facilities heat exchanger during the HFBR light-water flooding (LWF) event. While this event has a low probability (1.3 x 10{sup {minus}4}/yr), the HFBR protection system must ensure adequate thermal margin during the power transient. This paper summarizes the analysis of the HFBR thimble-tube LWF event.

• OSTI ID: 7168342
• Report Number(s): CONF-911107-; CODEN: TANSA; TRN: 92-030840
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics, San Francisco, CA (United States), 10-15 Nov 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HFBR REACTOR
EXPERIMENTAL CHANNELS
REACTOR SAFETY
BNL
FUEL ELEMENTS
GUIDE TUBES
HEAT EXCHANGERS
HEAVY WATER
IRRADIATION CAPSULES
MODERATORS
NEUTRON DIFFUSION EQUATION
REACTIVITY INSERTIONS
REACTOR CORES
REACTOR PHYSICS
REACTOR PROTECTION SYSTEMS
RUPTURES
TIME DEPENDENCE
TRANSIENTS
TUBES
WATER
DIFFERENTIAL EQUATIONS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUATIONS
FAILURES
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
HYDROGEN COMPOUNDS
NATIONAL ORGANIZATIONS
OXYGEN COMPOUNDS
PHYSICS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
TANK TYPE REACTORS
THERMAL REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors