Once-through CANDU reactor models for the ORIGEN2 computer code

Technical Report · Sat Nov 01 04:00:00 EST 1980

DOI:https://doi.org/10.2172/6918659· OSTI ID:6918659

Croff, A. G.; Bjerke, M. A.

Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2 computer code. The model CANDUs are based on (1) the existing once-through fuel cycle with feed comprised of natural uranium and (2) a projected slightly enriched (1.2 wt % /sup 235/U) fuel cycle. 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 ORIGEN2 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: 6918659
• Report Number(s): ORNL/TM-7177
• Country of Publication: United States
• Language: English

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