Modified Laser and Thermos cell calculations on microcomputers

Conference · Thu Jan 01 04:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6946777

Shapiro, A; Huria, H C

In the course of designing and operating nuclear reactors, many fuel pin cell calculations are required to obtain homogenized cell cross sections as a function of burnup. In the interest of convenience and cost, it would be very desirable to be able to make such calculations on microcomputers. In addition, such a microcomputer code would be very helpful for educational course work in reactor computations. To establish the feasibility of making detailed cell calculations on a microcomputer, a mainframe cell code was compiled and run on a microcomputer. The computer code Laser, originally written in Fortran IV for the IBM-7090 class of mainframe computers, is a cylindrical, one-dimensional, multigroup lattice cell program that includes burnup. It is based on the MUFT code for epithermal and fast group calculations, and Thermos for the thermal calculations. There are 50 fast and epithermal groups and 35 thermal groups. Resonances are calculated assuming a homogeneous system and then corrected for self-shielding, Dancoff, and Doppler by self-shielding factors. The Laser code was converted to run on a microcomputer. In addition, the Thermos portion of Laser was extracted and compiled separately to have available a stand alone thermal code.

• Research Organization: Univ. of Cincinnati, OH (USA)
• OSTI ID: 6946777
• Report Number(s): CONF-8711195-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 55
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
BURNUP
COMPUTER CODES
COMPUTERIZED SIMULATION
COMPUTERS
CROSS SECTIONS
ELECTRONIC CIRCUITS
FUELS
GROUP THEORY
L CODES
MATHEMATICS
MICROELECTRONIC CIRCUITS
MICROPROCESSORS
MIXED OXIDE FUELS
ONE-DIMENSIONAL CALCULATIONS
PHYSICS
REACTOR PHYSICS
SIMULATION
SOLID FUELS
T CODES