NUCLEAR REACTOR DEPLETION PROGRAMS FOR THE PHILCO-2000 COMPUTER
Technical Report
·
OSTI ID:4030341
The CANDLE, TURBO, and DRACO depletion programs for the IBM-704 computer were extended to the Philco2000 computer as a set of consistent programs. The calculations are based on few-group neutron-diffusion theory in which the group- averaged macroscopic cross sections are computed from fitted few-group microscopic cross sections. The build-up or depletion of isotopic number densities describing the materials present is calculated from the fitted cross sections and the neutron flux. The flux is assumed to be constant over the time interval of each step and is recomputed for each succeeding step. Mesh point limitations are 500 points, 20.000 points, and 100,000 points for the one-, two-. and three-dimensional versions, respectively. (auth)
- Research Organization:
- Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
- DOE Contract Number:
- AT(11-1)-GEN-14
- NSA Number:
- NSA-15-016377
- OSTI ID:
- 4030341
- Report Number(s):
- WAPD-TM-221
- Country of Publication:
- United States
- Language:
- English
Similar Records
IMPUT PREPARATION FOR DIFFUSION-DEPLETION PROGRAMS ON THE PHILCO-2000 COMPUTER
DRACO--A THREE-DIMENSIONAL FEW-GROUP DEPLETION CODE FOR THE IBM-704
TURBO--A TWO-DIMENSIONAL FEW-GROUP DEPLETION CODE FOR THE IBM-704
Technical Report
·
Sat Dec 31 23:00:00 EST 1960
·
OSTI ID:4076804
DRACO--A THREE-DIMENSIONAL FEW-GROUP DEPLETION CODE FOR THE IBM-704
Technical Report
·
Sun Nov 30 23:00:00 EST 1958
·
OSTI ID:4292387
TURBO--A TWO-DIMENSIONAL FEW-GROUP DEPLETION CODE FOR THE IBM-704
Technical Report
·
Thu Oct 31 23:00:00 EST 1957
·
OSTI ID:4322147