Published 1991
| Version v1
Journal article
Safety aspects of BNL's high-flux beam reactor
Description
The High-Flux Beam Reactor (HFBR) is a 60-MW(thermal) research reactor designed to produce intense thermal neutron beams. The safety design of the HFBR is based on the automatic shutdown systems, defense-in-depth decay heat removal systems, light water flooding protection, and the reactor confinement system. The reactor power level is presently downrated from 60 to 35.4 MW until thermal-hydraulic tests can be performed to benchmark safety analyses. These analyses should allow Brookhaven National Laboratory to increase reactor power and maintain the criteria of no fuel damage during a design-bases LOCA
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Journal Page Range
- p. 384-385.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics.
- Dates
- 10-15 Nov 1991.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24016021
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BNL; CONTROL ELEMENTS; CRITICALITY; FUEL INTEGRITY; HEAVY WATER; HFBR REACTOR; LOSS OF COOLANT; NATURAL CONVECTION; NEUTRON BEAMS; NEUTRON FLUX; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR CORES; REACTOR SAFETY; THERMAL NEUTRONS
- Descriptors DEC
- ACCIDENTS; BARYONS; BEAMS; CONTROL SYSTEMS; CONVECTION; COOLING SYSTEMS; ELEMENTARY PARTICLES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAT TRANSFER; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; NATIONAL ORGANIZATIONS; NEUTRONS; NUCLEON BEAMS; NUCLEONS; OXYGEN COMPOUNDS; PARTICLE BEAMS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; TANK TYPE REACTORS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER
Optional Information
- Secondary number(s)
- CONF-911107--.