Review of thorium-U233 cycle thermal reactor benchmark studies
Description:
A survey is made of existing integral experiments for U233 systems and thorium-uranium based fuel systems. The aim is to understand to what extent they give a consistent test of ENDF/B-IV nuclear data. A principal result is that ENDF/B-IV leads to an underprediction of neutron leakage. Results from testing alternate thorium data sets are presented. For one evaluation due to Leonard, the results depict a possible growing discrepancy between measured integral parameters such as rho/sup 02/ and I/…
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Date:
March 1, 1980
Creator:
Ullo, J.J.; Hardy, J. Jr. & Steen, N.M.
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department