PREMOR: a point reactor exposure model computer code for survey analysis of power plant performance
The PREMOR computer code was written to exploit a simple, two-group point nuclear reactor power plant model for survey analysis. Up to thirteen actinides, fourteen fission products, and one lumped absorber nuclide density are followed over a reactor history. Successive feed batches are accounted for with provision for from one to twenty batches resident. The effect of exposure of each of the batches to the same neutron flux is determined.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5779567
- Report Number(s):
- ORNL-5580; TRN: 79-022166
- Country of Publication:
- United States
- Language:
- English
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PREMOR; two-group point reactor power plant model. [IBM360,370,303x; FORTRAN IV (97%) and Assembler (3%)]
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