Sources of Neutronics Data Involving Thorium and ²³³U and Light Water Moderation

Technical Report · Wed Nov 01 04:00:00 EST 1978

DOI:https://doi.org/10.2172/1072039· OSTI ID:1072039

Davenport, L. C. ^[1]

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1. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

A literature search has been conducted to locate sources of neutronics data for light water moderated systems which contain thorium and/or uranium-233. It is concluded that insufficient data is currently available to validate neutronics design methods for licensing the ²³³UO₂-ThO₂ fuel cycle in light water reactors. A summary of the neutronics data sources found is reported in this document. These sources include critical and exponential experiments with lattices of fuel rods containing ²³³U + Th or ²³⁵U + Th. A few experiments using homogeneous aqueous solutions of ²³³UO₂ (NO₃)₂ or ²³³UO₂F₂ are also included. The only critical lattice data using both ²³³U + Th came from the LWBR program. All these experiments were zoned radially and in most cases axially also. Geometrically clean lattice critical data were measured for the CETR and TUPE programs. Both series used ²³⁵UO₂-ThO(₂ pellets. A series of 21 exponential experiments using 3% ²³³UO₂ - 97% ThO₂ fuel vibratory compacted to 92% of theoretical density in Zircaloy-2 tubing was performed at BNL using both unpoisoned and boric acid poisoned H₂O moderator. For completeness, homogeneous systems are listed in which basic neutronics data have been measured. However, it is expected that most data concerning homogeneous systems will be applied to criticality safety problems rather than neutronics methods validation.

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: EY-76-C-06-1830
• OSTI ID: 1072039
• Report Number(s): PNL--2917
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
Nuclear Criticality Safety Program (NCSP)