SciTech Connect

Title: Summary of advanced LMR (Liquid Metal Reactor) evaluations: PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor)

Summary of advanced LMR (Liquid Metal Reactor) evaluations: PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor) In support of the US Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) has performed independent analyses of two advanced Liquid Metal Reactor (LMR) concepts. The designs, sponsored by the US Department of Energy (DOE), the Power Reactor Inherently Safe Module (PRISM) (Berglund, 1987) and the Sodium Advanced Fast Reactor (SAFR) (Baumeister, 1987), were developed primarily by General Electric (GE) and Rockwell International (RI), respectively. Technical support was provided to DOE, RI, and GE, by the Argonne National Laboratory (ANL), particularly with respect to the characteristics of the metal fuels. There are several examples in both PRISM and SAFR where inherent or passive systems provide for a safe response to off-normal conditions. This is in contrast to the engineered safety systems utilized on current US Light Water Reactor (LWR) designs. One important design inherency in the LMRs is the inherent shutdown'', which refers to the tendency of the reactor to transition to a much lower power level whenever temperatures rise significantly. This type of behavior was demonstrated in a series of unscrammed tests at EBR-II (NED, 1986). The second key design feature is the passive air cooling of the vessel to remove decay heat. These systems, designated RVACS in PRISM more » and RACS in SAFR, always operate and are believed to be able to prevent core damage in the event that no other means of heat removal is available. 27 refs., 78 figs., 3 tabs. « less
Authors: ; ; ; ; ;
Publication Date:
OSTI Identifier:OSTI ID: 5491968
Report Number(s):NUREG/CR-5364; BNL-NUREG--52197
ON: TI90001756; TRN: 89-030979
DOE Contract Number:AC02-76CH00016
Resource Type:Technical Report
Research Org:Nuclear Regulatory Commission, Washington, DC (USA). Div. of Regulatory Applications; Brookhaven National Lab., Upton, NY (USA)
Sponsoring Org:NRC
Country of Publication:United States
Language:English
Subject: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; LMFBR TYPE REACTORS; DESIGN; AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; DEFORMATION; FEEDBACK; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; L CODES; LOSS OF COOLANT; M CODES; MATHEMATICAL MODELS; PIPES; PUMPS; R CODES; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; RESEARCH PROGRAMS; SCRAM; SWELLING; ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; SHUTDOWN; SIMULATION 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210500 -- Power Reactors, Breeding; 990220 -- Computers, Computerized Models, & Computer Programs-- (1987-1989)