Hydrogen generation behavior in the LOFT FP-2 and other experiments; Comparative assessment for mitigated severe accident conditions
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:5777159
- Engineering Science and Analysis, Albuquerque, NM (US)
In this paper Zircaloy oxidation and hydrogen generation data for the loss-of-fluid test (LOFT) FP-2 test are presented and compared with findings from other severe fuel damage experiments. In the LOFT FP-2 test, the majority of hydrogen generation occurred as a consequence of bundle reflooding, where significant hydrogen production was also noted in other reflood experiments and in the Three Mile Island Unit 2 accident. Common findings also indicate that during fuel uncovery, bundle oxidation is largely controlled by steam supply conditions, that high rates of hydrogen production continue after melt formation and relocation, and that partial flow-area blockages do not drastically reduce the rates of hydrogen production. Tests results thus indicate no apparent limitations to Zircaloy oxidation other than that due to steam supply conditions and known reaction kinetics, and that the potential for significant hydrogen generation exists during reflooding of cores containing molten metallic debris.
- OSTI ID:
- 5777159
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 97:1; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
Similar Records
Severe accident zircaloy oxidation/hydrogen generation behavior noted from in-pile test data
In-vessel Zircaloy oxidation/hydrogen generation behavior during severe accidents
Summary of important results and SCDAP/RELAP5 analysis for OECD LOFT experiment LP-FP-2
Journal Article
·
Thu Jan 31 23:00:00 EST 1991
· Nuclear Technology; (United States)
·
OSTI ID:5105002
In-vessel Zircaloy oxidation/hydrogen generation behavior during severe accidents
Technical Report
·
Sat Sep 01 00:00:00 EDT 1990
·
OSTI ID:6560378
Summary of important results and SCDAP/RELAP5 analysis for OECD LOFT experiment LP-FP-2
Technical Report
·
Thu Mar 31 23:00:00 EST 1994
·
OSTI ID:10147963
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
COMPARATIVE EVALUATIONS
CONTROL
ELEMENTS
ENRICHED URANIUM REACTORS
EVALUATION
FLOOD CONTROL
HYDROGEN
INHIBITION
LOFT REACTOR
NONMETALS
OXIDATION
POWER REACTORS
PRODUCTION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
ROD BUNDLES
STEAM SYSTEMS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
COMPARATIVE EVALUATIONS
CONTROL
ELEMENTS
ENRICHED URANIUM REACTORS
EVALUATION
FLOOD CONTROL
HYDROGEN
INHIBITION
LOFT REACTOR
NONMETALS
OXIDATION
POWER REACTORS
PRODUCTION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
RESEARCH AND TEST REACTORS
ROD BUNDLES
STEAM SYSTEMS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS