Improved Numerical Techniques for Processing Monte Carlo Thermal Scattering Data

Conference · Mon Nov 17 00:00:00 EST 1980

OSTI ID:5136036

Schmidt, Eldon ^[1]; Rose, Philip ^[1]

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1. Brookhaven National Laboratory (BNL), Upton, NY (United States)

As part of a Thermal Benchmark Validation Program sponsored by the Electric Power Research Institute (EPRI), the National Nuclear Data Center has been calculating thermal reactor lattices using the SAM-F Monte Carlo Computer Code. As part of this program a significant improvement has been made in the adequacy of the numerical procedures used to process the thermal differential scattering cross sections for hydrogen bound in H₂O.

• Research Organization: Brookhaven National Laboratory (BNL), Upton, NY (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5136036
• Report Number(s): BNL-28048; CONF-801107-11; TRN: 80-016723
• Resource Relation: Conference: ANS International Conference , Washington, DC (United States), 17-21 Nov 1980
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
REACTOR KINETICS
CROSS SECTIONS
THERMAL REACTORS
WATER MODERATED REACTORS
COMPUTER CALCULATIONS
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
REACTOR LATTICES
KINETICS
REACTORS
Nuclear Criticality Safety Program (NCSP)
Thermal Benchmark Validation Program
SAM-F Monte Carlo Computer Code
220100* - Nuclear Reactor Technology- Theory & Calculation