BURNUP; heavy element isotopic burnup analysis. [GE635; FORTRAN IV]

Technical Report ·

OSTI ID:6343495

Fowler, T B; Tobias, M L; Fox, J N; Lawler, B E; Koppel, J U; Triplett, J R; Lynn, L L; Waldman, L A; Goldberg, I; Greebler, P; Kelley, M D; Davis, R A; Keck, C E; Redfield, J A; Murphy,; McLaughlin, T V

BURNUP correlates heavy element isotopic analysis with fission product neodymium, uranium, and plutonium concentrations in an irradiated uranium fuel for calculation of burnup (atom per cent fission and MWD/MT). Reactor parameters, including effective neutron absorption cross sections for all uranium and plutonium isotopes, capture-to-fission ratios for U235, Pu239, and Pu241, a two-group description of the neutron spectrum, the average neutron temperature, the reactor fast fission factor, and the distribution of the sources of fission among the fissionable nuclides are computed from the experimental data obtained from the mass spectrometric analysis of uranium, plutonium, and neodymium.GE635; FORTRAN IV; GECOS; 32K memory and an on-line printer.

• Research Organization: General Electric Co., Pleasanton, CA (USA). Vallecitos Nucleonics Lab.
• OSTI ID: 6343495
• Report Number(s): ANL/NESC-311; ON: DE83048311
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ACTINIDE ISOTOPES
B CODES
BURNUP
COMPUTER CODES
FISSION PRODUCTS
FUELS
ISOTOPES
MASS SPECTROMETERS
MATERIALS
MEASURING INSTRUMENTS
PLUTONIUM ISOTOPES
RADIOACTIVE MATERIALS
SPECTROMETERS
URANIUM ISOTOPES