FORIG: a computer code for calculating radionuclide generation and depletion in fusion and fission reactors. User's manual

Technical Report · Fri Mar 01 00:00:00 EST 1985

DOI:https://doi.org/10.2172/6294299· OSTI ID:6294299

Blink, J A

In this manual we describe the use of the FORIG computer code to solve isotope-generation and depletion problems in fusion and fission reactors. FORIG runs on a Cray-1 computer and accepts more extensive activation cross sections than ORIGEN2 from which it was adapted. This report is an updated and a combined version of the previous ORIGEN2 and FORIG manuals. 7 refs., 15 figs., 13 tabs.

• Research Organization: Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6294299
• Report Number(s): UCRL-53633; ON: DE86005296
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
• Country of Publication: United States
• Language: English

Related Subjects

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THERMONUCLEAR REACTORS
FISSION
HEALTH HAZARDS
ISOTOPE SEPARATION
HAZARDS
NUCLEAR REACTIONS
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700206* - Fusion Power Plant Technology- Environmental Aspects
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220500 - Nuclear Reactor Technology- Environmental Aspects