Analysis of transient overpower accidents in the Fast Test Reactor using the Los Alamos Failure Model
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5532962
A new fuel pin failure model, the Los Alamos Failure Model (LAFM), based on a linear life fraction rule failure criterion, has been developed to provide a reliable and inexpensive prediction of the time and axial location of liquid-metal fast breeder reactor fuel pin failure in a hypothetical transient overpower (TOP) accident. Code testing analyses for a number of TOP Transient Reactor Test Facility tests have resulted in excellent agreement between calculated and observed pin failure time and location. Because of the nature of the failure criterion used, the code has also been used to investigate the extent of cladding damage incurred in terminated as well as unterminated TOP transients in the Fast Test Reactor. The results of these analyses show that 3 dollar/s and 50 and 5 cent/s transients terminated by the secondary trip point (25% overpower) result in negligible calculated cladding damage.
- Research Organization:
- Los Alamos Scientific Lab., NM
- OSTI ID:
- 5532962
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 46:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of terminated TOP accidents in the FTR using the Los Alamos failure model
Simple computational model for the prediction of fuel pin failure during a transient-overpower accident. [LMFBR]
Calibration and qualification of the Los Alamos Failure Model (LAFM). [LMFBR]
Conference
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6412559
Simple computational model for the prediction of fuel pin failure during a transient-overpower accident. [LMFBR]
Thesis/Dissertation
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5416229
Calibration and qualification of the Los Alamos Failure Model (LAFM). [LMFBR]
Technical Report
·
Tue May 01 00:00:00 EDT 1984
·
OSTI ID:6686881
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
MATHEMATICAL MODELS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TIME DEPENDENCE
TRANSIENT OVERPOWER ACCIDENTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
LIQUID METAL COOLED REACTORS
MATHEMATICAL MODELS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TIME DEPENDENCE
TRANSIENT OVERPOWER ACCIDENTS