ORIGEN2: A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials

Journal Article · Thu Sep 01 04:00:00 EDT 1983 · Nucl. Technol.; (United States)

OSTI ID:5421763

Croff, A G

ORIGEN2 is a versatile point-depletion and radioactive-decay computer code for use in simulating nuclear fuel cycles and calculating the nuclide compositions and characteristics of materials contained therein. It represents a revision and update of the original ORIGEN computer code, which was developed at the Oak Ridge National Laboratory (ORNL) and distributed worldwide beginning in the early 1970s. Included in ORIGEN2 are provisions for incorporating data generated by more sophisticated reactor physics codes, a free-format input, and a highly flexible and controllable output; with these features, ORIGEN2 has the capability for simulating a wide variety of fuel cycle flow sheets. The decay, cross-section, fission product yield, and photon emission data bases employed by ORIGEN2 have been extensively updated, and the list of reactors that can be simulated includes pressurized water reactors, boiling water reactors, liquid-metal fast breeder reactors, and Canada deuterium uranium reactors. A number of verification activities have been undertaken, including comparison of ORIGEN2 decay heat results with both calculated and experimental values, and comparison of predicted spent fuel compositions with measured values. The agreement between ORIGEN2 and the comparison bases is generally very good.

• Research Organization: Oak Ridge National Laboratory, Chemical Technology Division, P.O. Box X, Oak Ridge, Tennessee 37830
• OSTI ID: 5421763
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 62:3; ISSN NUTYB
• Country of Publication: United States
• Language: English

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