Alternative fuel cycle PWR models for the ORIGEN computer code

Technical Report · Fri Feb 01 04:00:00 UTC 1980

OSTI ID:5627539

Croff, A G; Bjerke, M A

Reactor physics calculations have led to the development of four PWR models for the ORIGEN computer code. The PWRs operate on the following fuel cycles: (1) denatured /sup 233/U-thorium oxide; (2) plutonium-thorium oxide; (3) low-enrichment uranium oxide with an extended burnup; and (4) thorium oxide enriched with self-generated, denatured /sup 233/U and denatured /sup 235/U. The reactor models are based on cross sections taken directly from the reactor physics codes. Descriptions of the reactor models, as well as values for the ORIGEN flux parameters THERM, RES, and FAST, are given.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5627539
• Report Number(s): ORNL/TM-7005
• Country of Publication: United States
• Language: English

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