Evaluation of initial temperature effect on transient fuel behavior under simulated reactivity-initiated accident conditions
- 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)
Description
In order to evaluate possible effects of initial temperature on the transient fuel behavior, such as cladding deformation and fission gas release, under reactivity-initiated accident conditions, two comparative pulse-irradiation tests were performed on identical high-burnup PWR fuel rods under different temperature conditions at the Nuclear Safety Research Reactor (NSRR). The test RH-1 was carried out at room temperature of ∼20degC, while the coolant temperature in the test RH-2 was ∼280degC corresponding to the hot zero power temperature of PWR. The fuel rods did not fail in both tests against fuel enthalpy increases of 462 and 378 J/g, respectively. The results of the two tests were generally consistent with data previously obtained in a number of tests at room temperature, when the data were plotted as a function of the peak fuel enthalpy, not of the maximum increase in fuel enthalpy. Computer analysis using the RANNS code confirmed that the cladding residual deformation in the test RH-2 was driven only by the pellet thermal expansion and that the gas-induced deformation did not occur because the cladding temperature did not become high enough to enhance creep deformation even in the film boiling on the cladding surface. (author)
Availability note (English)
Available from http://dx.doi.org/10.3327/jnst.47.439Additional details
Identifiers
- DOI
- 10.3327/jnst.47.439;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 47
- Journal Issue
- 5
- Journal Page Range
- p. 439-448
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 41130398
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DEFORMATION; FISSION PRODUCT RELEASE; FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; NSRR REACTOR; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENT SIMULATION; REACTOR ACCIDENTS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MIXED SPECTRUM REACTORS; POWER REACTORS; PULSED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 refs., 12 figs., 4 tabs.