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:6475959

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 ORGEN2 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 (a) comparison of ORIGEN2 decay heat results with both calculated and experimental values, and (b) comparison of predicted spent fuel compositions with measured values. The agreement between ORIGEN2 and the comparison bases is generally very good. Future work concerning ORIGEN2 will involve continued maintenance and user support along with additional verification studies and limited modifications to enhance its flexibility and usability. ORIGEN2 can be obtained, free of charge, from the ORNL Radiation Shielding Information Center.

• Research Organization: Oak Ridge National Lab., Chemical Technology Division, Oak Ridge, TN
• OSTI ID: 6475959
• 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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ACTINIDES
AFTER-HEAT
BREEDER REACTORS
BWR TYPE REACTORS
CANDU TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
DECAY
DEUTERIUM
DIAGRAMS
ELEMENTS
EMISSION
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FLOWSHEETS
FUEL CYCLE
FUELS
HEAVY WATER MODERATED REACTORS
HYDROGEN ISOTOPES
ISOTOPES
KINETICS
LIGHT NUCLEI
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
NUCLEI
O CODES
ODD-ODD NUCLEI
ORNL
PHOTON EMISSION
PRESSURE TUBE REACTORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVITY
REACTOR KINETICS
REACTOR MATERIALS
REACTORS
SIMULATION
STABLE ISOTOPES
THERMAL REACTORS
URANIUM
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS