Summary of important results and SCDAP/RELAP5 analysis for OECD LOFT experiment LP-FP-2
Creators
- 1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
Description
This report summarizes significant technical findings from the LP-FP-2 Experiment sponsored by OECD. It was the second, and final, fission product experiment conducted in the Loss-of-Fluid Test (LOFT) facility at the Idaho National Engineering Laboratory. The overall technical objective of the test was to contribute to the understanding of fuel rod behavior, hydrogen generation, and fission product release, transport, and deposition during a V-sequence accident scenario that resulted in severe core damage. An 11 by 11 test bundle, comprised of 100 pre-pressurized fuel rods, 11 control rods, and 10 instrumented guide tubes, was surrounded by an insulating shroud and contained in a specially designed central fuel module, that was inserted into the LOFT reactor. The simulated transient was a V-sequence loss-of-coolant accident scenario featuring a pipe break in the low pressure injection system line attached to the hot leg of the LOFT broken loop piping. The transient was terminated by reflood of the reactor vessel when the outer wall shroud temperature reached 1517 K. With sustained fission power and heat from oxidation and metal-water reactions, elevated temperatures resulted in zircaloy melting, fuel liquefaction, material relocation, and the release of hydrogen, aerosols, and fission products. A description and evaluation of the major phenomena, based upon the response of on line instrumentation, analysis of fission product data, post-irradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented
Files
41025204.pdf
Files
(10.9 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 170 p.
- Report number
- NEA-CSNI-R--1994-3
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 41025204
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; FISSION PRODUCT RELEASE; FUEL RODS; HYDROGEN; LOFT REACTOR; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; RADIOACTIVE AEROSOLS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; S CODES; SOURCE TERMS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; COMPUTER CODES; COOLING SYSTEMS; DISPERSIONS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; MECHANICS; NONMETALS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 27 refs.