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Experimental and Calculated Results for UO2 and UO2-PuO2 Fueled H2O-Moderated Loadings

Technical Report ·
DOI:https://doi.org/10.2172/4112503· OSTI ID:4112503
 [1];  [1];  [1];  [2];  [2]
  1. Comitato Nazionale per l'Energia Nucleare (CNEN), Frascati (Italy)
  2. Battelle Pacific Northwest Labs., Richland, WA (United States)
This report contains data collected during a series of experiments in the Plutonium Recycle Critical Facility (PRCF) using plutonium and uranium enriched fuel. The experiments were designed to provide a base for assessing the accuracy of calculational techniques used for designing plutonium enriched cores in Boiling Water Reactors with regard to predicting core reactivities, power distributions, and control system worths. Reactivity and power distribution measurements were made in both single region and multiregion loadings. Calorimetric techniques were used to intercalibrate the different fuel types for the multiregion loadings. The reactivity effect of various control blade materials was determined as a function of the prompt neutron decay rate (Rossi-Alpha). Theory-experimental comparisons are based primarily on CNEN developed theoretical models.
Research Organization:
Battelle Pacific Northwest Labs., Richland, WA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
DOE Contract Number:
AT(45-1)-1830
NSA Number:
NSA-24-047820
OSTI ID:
4112503
Report Number(s):
BNWL-1379
Country of Publication:
United States
Language:
English