Method for generating neutronic data bases for transient reactor calculations

Conference · Thu Jan 01 00:00:00 EST 1976

OSTI ID:7231286

Buckner, M. R.; Parks, P. B.

A method has been devised for the generation of neutronic data bases for use in reactor transient calculations using diffusion theory. The method makes use of scientific knowledge and experience in the trial and error approach to the correlation process. The data requirements for the support of the data base are made practical by the use of the multi-regime concept and the application of the Box-Behnken or other incomplete factorial design concepts. The method has been thoroughly tested and has been found to produce adequate representations of the fewgroup cross sections for detailed transient analysis studies with multidimensional reactor code systems.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
• DOE Contract Number: E(07-2)-1
• OSTI ID: 7231286
• Report Number(s): DP-MS-76-71; CONF-770304-1; TRN: 77-006201
• Resource Relation: Conference: Analysis of nuclear systems, Tucson, AZ, USA, 28 Mar 1977
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR KINETICS
DATA COMPILATION
COMPUTER CALCULATIONS
CORRELATIONS
K REACTOR
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
P REACTOR
R REACTOR
TRANSIENTS
HEAVY WATER MODERATED REACTORS
KINETICS
NEUTRON TRANSPORT THEORY
PRODUCTION REACTORS
REACTORS
SPECIAL PRODUCTION REACTORS
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation