Review of the SIMMER-II Analyses of Liquid-Metal-Cooled Fast Breeder Reactor Core-Disruptive Accident Fuel Escape
Conference
·
OSTI ID:5869134
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States). University of California
Early fuel removal from the active core of a liquid-metal-cooled fast breeder reactor undergoing a core-disruptive accident may reduce the potential for large energetics resulting from recriticalities. This paper presents a review of analyses with the SIMMER-II computer program of the effectiveness of possible fuel escape paths. Where possible, how SIMMER-II compares with or is validated against experiments that simulated the escape paths also is discussed.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States). University of California
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5869134
- Report Number(s):
- LA-UR-85-1341; CONF-850410-37; ON: DE85010803
- Resource Relation:
- Conference: ANS/ENS Fast Reactor Safety Meeting , Knoxville, TN (United States), 21 Apr 1985; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of the calculated results of an unprotected transient undercooling accident in a large, heterogeneous-core, liquid-metal-cooled fast breeder reactor
An assessment of Clinch River Breeder Reactor core disruptive accident energetics
SIMMER-II recriticality analyses for a homogeneous core of the 300-MW (electric) class
Technical Report
·
Wed Dec 01 00:00:00 EST 1982
·
OSTI ID:5869134
+1 more
An assessment of Clinch River Breeder Reactor core disruptive accident energetics
Journal Article
·
Tue Jul 01 00:00:00 EDT 1986
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:5869134
SIMMER-II recriticality analyses for a homogeneous core of the 300-MW (electric) class
Journal Article
·
Tue Nov 01 00:00:00 EST 1983
· Nucl. Technol.; (United States)
·
OSTI ID:5869134
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
LMFBR TYPE REACTORS
REACTOR CORE DISRUPTION
COMPUTER CODES
CRITICALITY
NUCLEAR FUELS
REMOVAL
S CODES
ACCIDENTS
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
LIQUID METAL COOLED REACTORS
MATERIALS
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTORS
Nuclear Criticality Safety Program (NCSP)
Early Fuel Removal
SIMMER-II Computer Program
Analyses Review
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
LMFBR TYPE REACTORS
REACTOR CORE DISRUPTION
COMPUTER CODES
CRITICALITY
NUCLEAR FUELS
REMOVAL
S CODES
ACCIDENTS
BREEDER REACTORS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
LIQUID METAL COOLED REACTORS
MATERIALS
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTORS
Nuclear Criticality Safety Program (NCSP)
Early Fuel Removal
SIMMER-II Computer Program
Analyses Review
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding