Physics analysis of PBF test RIA 1-3 (PNL hardware). [BWR]
The Reactor Safety Research Program of the Nuclear Regulatory Commission includes a series of transient experiments in the Power Burst Facility (PBF) to investigate the fuel failure modes and consequences of postulated Reactivity Initiated Accidents (RIA) in large power reactors. The most severe RIA postulated is the boiling water reactor (BWR) control rod drop accident during startup; therefore the series 1 tests are to be conducted under BWR startup conditions. In RIA 1-3 each of the four unirradiated BWR/6-type fuel pins will be surrounded by a separate flow shroud. Two of the pins will be enriched to 3.6 wt%; the other two, to 4.2 wt% /sup 235/U. The immediate objectives of this work are to determine the azimuthal and radial power distribution and Figure of Merit (ratio of axial peak energy deposition in the test fuel (J/g) to the driver fuel energy release (MJ) for each of the two types of fuel pins in the RIA 1-3 test assembly.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6322188
- Report Number(s):
- RE-P-78-086
- Country of Publication:
- United States
- Language:
- English
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