Reactivity feedback from irradiated pin failure in unprotected slow TOP accidents in LMFBR's
Conference
·
OSTI ID:5913668
The present work is an outgrowth of studies made in support of CRBR licensing, but the conclusions drawn should be generally applicable to oxide-fueled LMFBR's. The accident under consideration is a 10 cents/s unprotected TOP (transient overpower), for which a series of PLUTO2/SAS4A calculations has been performed using a higher power CRBR EOC3 fuel pin which had 275 days irradiation. The assumption was made in the licensing work that a short pin failure will occur at the axial midplane, maximizing the positive fuel motion reactivity effect, as it was felt that a less conservative assumption could not be conclusively justified. This assumption is also made in the present case.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5913668
- Report Number(s):
- CONF-850410-3; ON: DE85000074
- Resource Relation:
- Conference: ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985
- Country of Publication:
- United States
- Language:
- English
Similar Records
Post-failure phenomena in LMFBR TOP accidents. Annual report, July 1, 1975--June 30, 1976
SAS4A and FPIN2X validation for slow ramp TOP accidents: experiments TS-1 and TS-2
Survival of peripheral pins during a TOP-HCDA. [LMFBR]
Technical Report
·
Sat Jan 01 00:00:00 EST 1977
·
OSTI ID:5913668
SAS4A and FPIN2X validation for slow ramp TOP accidents: experiments TS-1 and TS-2
Conference
·
Wed Jan 01 00:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5913668
Survival of peripheral pins during a TOP-HCDA. [LMFBR]
Conference
·
Sun Jul 01 00:00:00 EDT 1979
·
OSTI ID:5913668
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PINS
PRESSURE GRADIENTS
THERMAL STRESSES
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
BURNUP
COMPUTER CALCULATIONS
FUEL ELEMENT FAILURE
REACTIVITY WORTHS
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PINS
PRESSURE GRADIENTS
THERMAL STRESSES
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
BURNUP
COMPUTER CALCULATIONS
FUEL ELEMENT FAILURE
REACTIVITY WORTHS
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding