Decay heat measurements and predictions of BWR spent fuel
Pre-calorimetry decay heat predictions obtained with the ORIGEN2 computer code were compared to calorimeter data obtained for eleven boiling water reactor (BWR) spent fuel assemblies using General Electric, Morris Operation's in-pool calorimeter. Ten of the 7 x 7 BWR spent fuel assemblies were obtained from Nebraska Public Power District's Cooper Nuclear Station. The remaining BWR assembly was from Commonwealth Edison's Dresden Nuclear Power Plant. The assemblies had burnups ranging from 5.3 to 27.6 GWD/MTU and had been removed from their respective reactors for 2 or more years. The majority of the assemblies had burnups of between 20 and 28 GWD/MTU and had been out of the reactor 2 to 4 years. The assemblies represent spent fuel that has been continuously burned and fuel that has been reinserted. Comparisons of ORIGEN2 pre-calorimetry decay heat predictions with calorimeter data showed that predictions agreed with data within the precision/repeatibility of the experimental data (+-15 Watts or 5% for a 300 Watt BWR assembly). Comparisons of predicted axial gamma profiles based on core-averaged axial burnups with measured profiles showed difference. These differences may be explained by reactor operation with partially inserted control rods.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5551145
- Report Number(s):
- EPRI-NP-4619; ON: DE86012266
- Country of Publication:
- United States
- Language:
- English
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210100* -- Power Reactors
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AFTER-HEAT REMOVAL
BWR TYPE REACTORS
CALORIMETRY
COMPUTER CODES
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ENERGY SOURCES
ENTHALPY
FUELS
MATERIALS
MEASURING METHODS
NUCLEAR FUELS
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PHYSICAL PROPERTIES
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