Summary of advanced LMR [Liquid Metal Reactor] evaluations: PRISM [Power Reactor Inherently Safe Module] and SAFR [Sodium Advanced Fast Reactor]
Creators
- 1. Brookhaven National Lab., Upton, NY (USA)
Description
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 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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A07/MF A01 - GPO as TI90001756; OSTI; INIS.Files
21019345.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 120 p.
- Report number
- NUREG/CR--5364
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21019345
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; DEFORMATION; FEEDBACK; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; L CODES; LMFBR TYPE REACTORS; LOSS OF COOLANT; M CODES; MATHEMATICAL MODELS; PIPES; PUMPS; R CODES; REACTIVITY; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR SHUTDOWN; RESEARCH PROGRAMS; SCRAM; SPECIFICATIONS; SWELLING
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SHUTDOWN; SIMULATION
Optional Information
- Contract/Grant/Project number
- Contract AC02-76CH00016
- Secondary number(s)
- BNL-NUREG--52197.