Light water reactor fuel response during reactivity initiated accident experiments
Experimental results from six recent Power Burst Facility (PBF) reactivity initiated accident (RIA) tests are compared with data from previous SPERT, TREAT and NSRR programs. The RIA fuel behavior experimental program recently started in the PBF is being conducted with coolant conditions typical of hot-startup conditions in a commercial boiling water reactor. The SPERT, TREAT and NSRR test programs investigated the behavior of single or small clusters of light water reactor (LWR) type fuel rods under approximate room temperature and atmospheric pressure conditions in capsules containing stagnant water. As observed in the previous tests, energy depositions, and consequent enthalpy increase, in the PBF test fuel appears to be the single most important variable. However, the consequences of failure at boiling water hot-startup system conditions appear to be more severe than previously observed in either the stagnant SPERT or NSRR tests. Metallographic examination of both previously unirradiated and irradiated PBF fuel rod cross sections revealed extensive variation in cladding wall thickness involving considerable plastic flow and fuel shattering along grain boundaries in both restructured and unrestructured fuel regions. In addition, swelling of the gaseous and potentially volatile fission products in previously irradiated fuel resulted in volume increases of up to 180% and blockage of the flow shrouds surrounding the fuel rods.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6272431
- Report Number(s):
- CONF-790441-3; TRN: 79-012892
- Resource Relation:
- Conference: ANS topical meeting on light water reactor fuel performance, Portland, OR, USA, 29 Apr 1979
- Country of Publication:
- United States
- Language:
- English
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