FUEL BURN-UP STUDY OF HNPF REFERENCE CORE
Technical Report
·
OSTI ID:4014304
The change of reactivity in the Hallam Power Reactor is calculated as a function of exposure, up to an average exposure of 8000 Mwd/t. The numbers of U/ sup 235/, Pu/sup 239/, and Pu/sup 241/ atoms, relative to the original number of U/sup 235/ ato ms, are also calculated as functions of exposure. The fuel is assumed to be un-recycled, and the control rods are assumed to be fully withdrawn. The effects of fission products other than Xe and Sm are accounted for. (T.F.H.)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- NSA Number:
- NSA-15-025639
- OSTI ID:
- 4014304
- Report Number(s):
- NAA-SR-Memo-3228
- Country of Publication:
- United States
- Language:
- English
Similar Records
FUEL BURN-UP STUDY OF THE U-MOLY.FUELED HALLAM REFERENCE CORE
EFFECTIVE CROSS SECTION VALUES FOR WELL-MODERATED THERMAL REACTOR SPECTRA. (1958 Revision)
ENERGY-DEPENDENT AND SPECTRUM-AVERAGED THERMAL CROSS SECTIONS FOR THE HEAVY ELEMENTS AND FISSION PRODUCTS FOR VARIOUS TEMPERATURES AND C: U$sup 235$ ATOM RATIOS
Technical Report
·
Sun Jan 25 23:00:00 EST 1959
·
OSTI ID:4188830
EFFECTIVE CROSS SECTION VALUES FOR WELL-MODERATED THERMAL REACTOR SPECTRA. (1958 Revision)
Technical Report
·
Fri Aug 01 00:00:00 EDT 1958
·
OSTI ID:4301688
ENERGY-DEPENDENT AND SPECTRUM-AVERAGED THERMAL CROSS SECTIONS FOR THE HEAVY ELEMENTS AND FISSION PRODUCTS FOR VARIOUS TEMPERATURES AND C: U$sup 235$ ATOM RATIOS
Technical Report
·
Fri Jun 16 00:00:00 EDT 1961
·
OSTI ID:4841912