Summary of advanced LMR (Liquid Metal Reactor) evaluations: PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor)
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 … continued below
Physical Description
Pages: (120 p)
Creation Information
Van Tuyle, G. J.; Slovik, G. C.; Chan, B. C.; Kennett, R. J.; Cheng, H. S. & Kroeger, P. G. October 1, 1989.
Context
This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by the UNT Libraries Government Documents Department to the UNT Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 161 times. More information about this report can be viewed below.
Who
People and organizations associated with either the creation of this report or its content.
Authors
- Van Tuyle, G. J.
- Slovik, G. C.
- Chan, B. C.
- Kennett, R. J.
- Cheng, H. S.
- Kroeger, P. G. (Brookhaven National Lab., Upton, NY (USA))
Sponsor
Publishers
-
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Regulatory Applications
Place of Publication: United States
-
Brookhaven National Laboratory
Publisher Info: Brookhaven National Lab., Upton, NY (USA)Place of Publication: Upton, New York
Provided By
UNT Libraries Government Documents Department
Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.
Contact Us
What
Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.
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.
Physical Description
Pages: (120 p)
Notes
NTIS, PC A07/MF A01 - GPO; OSTI; INIS
Subjects
Keywords
- Accidents
- After-Heat Removal
- Breeder Reactors
- Computer Codes
- Computerized Simulation
- Control Elements
- Cooling Systems
- Deformation
- Design
- Energy Systems
- Energy Transfer
- Epithermal Reactors
- Fast Reactors
- Fbr Type Reactors
- Feedback
- Fluid Flow
- Fluid Mechanics
- Heat Transfer
- Hydraulics
- L Codes
- Liquid Metal Cooled Reactors
- Lmfbr Type Reactors
- Loss Of Coolant
- M Codes
- Mathematical Models
- Mechanics
- Pipes
- Pumps
- R Codes
- Reactivity
- Reactor Accidents
- Reactor Components
- Reactor Cooling Systems
- Reactor Safety
- Reactor Shutdown
- Reactors
- Removal
- Research Programs
- Safety
- Scram
- Shutdown
- Simulation 220900* -- Nuclear Reactor Technology-- Reactor Safety
- Swelling
STI Subject Categories
Language
Item Type
Identifier
Unique identifying numbers for this report in the Digital Library or other systems.
- Other: TI90001756
- Report No.: NUREG/CR-5364
- Report No.: BNL-NUREG--52197
- Grant Number: AC02-76CH00016
- Digital Object Identifier: https://doi.org/10.2172/5491968
- Office of Scientific & Technical Information Report Number: 5491968
- Archival Resource Key: ark:/67531/metadc1085233
Collections
This report is part of the following collection of related materials.
Office of Scientific & Technical Information Technical Reports
Reports, articles and other documents harvested from the Office of Scientific and Technical Information.
Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.
Digital Files
When
Dates and time periods associated with this report.
Creation Date
- October 1, 1989
Added to The UNT Digital Library
- Feb. 10, 2018, 10:06 p.m.
Description Last Updated
- May 30, 2021, 5:34 p.m.
Usage Statistics
When was this report last used?
Interact With This Report
Here are some suggestions for what to do next.
Start Reading
Citations, Rights, Re-Use
International Image Interoperability Framework
We support the IIIF Presentation API
Print / Share
Links for Robots
Helpful links in machine-readable formats.
Archival Resource Key (ARK)
- ERC Record: /ark:/67531/metadc1085233/?
- Persistence Statement: /ark:/67531/metadc1085233/??
International Image Interoperability Framework (IIIF)
- IIIF Manifest: /ark:/67531/metadc1085233/manifest/
Metadata Formats
- UNTL Format: /ark:/67531/metadc1085233/metadata.untl.xml
- DC RDF: /ark:/67531/metadc1085233/metadata.dc.rdf
- DC XML: /ark:/67531/metadc1085233/metadata.dc.xml
- OAI_DC: /oai/?verb=GetRecord&metadataPrefix=oai_dc&identifier=info:ark/67531/metadc1085233
- METS: /ark:/67531/metadc1085233/metadata.mets.xml
- OpenSearch Document: /ark:/67531/metadc1085233/opensearch.xml
Images
- Thumbnail: /ark:/67531/metadc1085233/thumbnail/
- Small Image: /ark:/67531/metadc1085233/small/
URLs
- In-text: /ark:/67531/metadc1085233/urls.txt
Stats
- Usage Stats: /stats/stats.json?ark=ark:/67531/metadc1085233
Van Tuyle, G. J.; Slovik, G. C.; Chan, B. C.; Kennett, R. J.; Cheng, H. S. & Kroeger, P. G. Summary of advanced LMR (Liquid Metal Reactor) evaluations: PRISM (Power Reactor Inherently Safe Module) and SAFR (Sodium Advanced Fast Reactor), report, October 1, 1989; United States. (https://digital.library.unt.edu/ark:/67531/metadc1085233/: accessed July 2, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.