Review of thorium-U233 cycle thermal reactor benchmark studies (AWBA Development Program)

Technical Report · Sat Mar 01 00:00:00 EST 1980

DOI:https://doi.org/10.2172/5506237· OSTI ID:5506237

Ullo, J. J.; Hardy, J. Jr.; Steen, N. M.

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/sup 232/ and the differential data, which underpredicts these parameters. Sensitivities to other nuclear data components, notably the fission neutron spectrum, were determined. A new harder U233 spectrum significantly reduces a bias trend in K/sub eff/ vs leakage.

• Research Organization: Bettis Atomic Power Lab. (BAPL), West Mifflin, PA (United States)
• DOE Contract Number: AC11-76PN00014
• OSTI ID: 5506237
• Report Number(s): WAPD-TM-1456; TRN: 80-007926
• Country of Publication: United States
• Language: English

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