Effects of transient power histories on the intrasubassembly failure incoherencies
Conference
·
OSTI ID:5555464
The effects of different transient power histories on the intrasubassembly failure incoherencies in an unprotected Transient Overpower (TOP) Hypothetical Core Disruptive Accident (HCDA) are analyzed. The computational tool and other relevant points of present analysis are described. The computational results from the analysis are also discussed. The summary of the present study is stated.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 5555464
- Report Number(s):
- HEDL-SA-1868; CONF-791103-64
- Country of Publication:
- United States
- Language:
- English
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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
COMPUTER CALCULATIONS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLUID MECHANICS
FUEL ELEMENT FAILURE
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
STRESSES
TEST REACTORS
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLUID MECHANICS
FUEL ELEMENT FAILURE
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
STRESSES
TEST REACTORS
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS