Measurement and preliminary analysis on transient cladding deformation during reactivity initiated accident conditions
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
The transient cladding deformation measurement tests have been performed under reactivity initiated accident (RIA) conditions in the Nuclear Safety Research Reactor (NSRR). A single PWR type fuel rod which was instrumented with strain gage was contained within a capsule filled with water at ambient temperature and atmospheric pressure, and heated up by pulsing operation of the NSRR simulating an RIA. Transient diametral deformation of the cladding tube due to Pellet-Cladding Mechanical Interaction (PCMI) was successfully measured using strain gage. It was revealed through the experiments that strain gage designed for the use in steel could be applied for the measurement of transient PCMI behavior of zircaloy cladding tube if appropriate correction on temperature compensation of the strain gage was made. Data obtained by the strain gage are quite valuable for the verification of the fuel rod deformation model in the fuel behavior analysis code. Preliminary analysis showed that pellet deformation model of GAPCON-THERMAL-1 code gave good prediction on the fuel rod deformation under an RIA transient. (author)
Additional details
Publishing Information
- Journal Title
- J. Nucl. Sci. Technol. (Tokyo)
- Journal Volume
- 22
- Journal Issue
- 2
- Series
- J. Nucl. Sci. Technol. (Tokyo).
- Journal Page Range
- 81-92
- ISSN
- 0022-3131
- CODEN
- JNSTA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 17013359
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DEFORMATION; ENERGY DEPOSITION; FUEL CANS; FUEL ELEMENT FAILURE; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; NSRR REACTOR; REACTOR SAFETY EXPERIMENTS; STRAINS; TEMPERATURE DEPENDENCE; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MIXED SPECTRUM REACTORS; PULSED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS