Behavior of small-sized BWR fuel under reactivity initiated accident conditions
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
The present work was performed on this small-sized BWR fuel, where Zr liner and rod prepressurization were taken as experimental parameters. Experiment was done under simulated reactivity initiated accident (RIA) conditions at Nuclear Safety Research Reactor (NSRR) belonged to Japan Atomic Energy Research Institute (JAERI). Major remarks obtained are as follows: (1) Three different types of the fuel rods consisted of (a) Zr lined/pressurized (0.65MPa), (b) Zr lined/non-pressurized and (c) non-Zr lined/pressurized (o.65MPa) were used, respectively. Failure thresholds of these were not less than that (260 cal/g·fuel) described in Japanese RIA Licensing Guideline. Small-sized BWR and conventional 8 x 8 BWR fuels were considered to be in almost the same level in failure threshold. Failure modes of the three were (a) cladding melt/brittle, (b) cladding melt/brittle and (c) rupture by large ballooning, respectively. (2) The magnitude of pressure pulse at fuel fragmentation was also studied by lined/pressurized and non-lined/pressurized fuels. Above the energy deposition of 370 cal/g·fuel, mechanical energy (or pressure) was found to be released from these fragmented fuels. No measurable difference was, however, observed between the tested fuels and NSRR standard (and conventional 8 x 8 BWR) fuels. (3) It is worthy of mentioning that Zr liner tended to prevent the cladding from large ballooning. Non-lined/pressurized fuel tended to cause wrinkle deformation at cladding. Hence, cladding external was notched much by the wrinkles. (4) Time to fuel failure measured from the tested BWR fuels (pressurization < 0.6MPA) was longer than that measured from PWR fuels (pressurization < 3.2MPa). The magnitude of the former was of the order of 3 ∼ 6s, while that of the latter was < 1s. (J.P.N.)
Availability note (English)
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23031875.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 101 p.
- Report number
- JAERI-M--91-211
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 23031875
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BRITTLENESS; BWR TYPE REACTORS; DEFORMATION; FUEL ELEMENT FAILURE; FUEL RODS; HEATING; LINERS; METALLOGRAPHY; NSRR REACTOR; POST-IRRADIATION EXAMINATION; PRESSURIZATION; RECOMMENDATIONS; RUPTURES; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; ELEMENTS; ENRICHED URANIUM REACTORS; FAILURES; FUEL ELEMENTS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MECHANICAL PROPERTIES; METALS; MIXED SPECTRUM REACTORS; POWER REACTORS; PULSED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS