Validation of KENO V.a for Highly Enriched Uranium Systems with Hydrogen and/or Carbon Moderation
- Oak Ridge Y-12 Plant (Y-12), Oak Ridge, TN (United States)
- University of Tennessee, Knoxville, TN (United States). Nuclear Engineering Dept.
This paper describes the validation in accordance with ANSI/ANS-8.1-1983(R1988) of KENO V.a using the 27-group ENDF/B-IV cross-section library for systems containing highly-enriched uranium, carbon, and hydrogen and for systems containing highly-enriched uranium and carbon with high carbon to uranium (C/U) atomic ratios. The validation has been performed for two separate computational platforms: an IBM 3090 mainframe and an HP 9000 Model 730 workstation, both using the Oak Ridge Y-12 Plant Nuclear Criticality Safety Software (NCSS) code package. Critical experiments performed at the Oak Ridge Critical Experiments Facility, in support of the Rover reactor program, and at the Pajarito site at Los Alamos National Laboratory were identified as having the constituents desired for this validation as well as sufficient experimental detail to allow accurate construction of KENO V.a calculational models. Calculated values of keff for the Rover experiments, which contain uranium, carbon, and hydrogen, are between 1.0012 ± 0.0026 and 1.0245 ± 0.0023. Calculation of the Los Alamos experiments, which contain uranium and carbon at high C/U ratios, yields values of keff between 0.9746 ± 0.0028 and 0.9983 ± 0.0027. Safety criteria can be established using this data for both types of systems.
- Research Organization:
- Oak Ridge Y-12 Plant (Y-12), Oak Ridge, TN (United States); University of Tennessee, Knoxville, TN (United States). Nuclear Engineering Dept.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-84OS21400
- OSTI ID:
- 10107565
- Report Number(s):
- Y/DD--607; CONF-930907--14; ON: DE94003326
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
420203
97 MATHEMATICS AND COMPUTING
990301
ANSI/ANS-8.1-1983(R1988)
COMPUTERIZED SIMULATION
CRITICALITY
CROSS SECTIONS
DATA HANDLING
ENDF/B-IV
FISSIONABLE MATERIALS
HANDLING EQUIPMENT AND PROCEDURES
HIGHLY ENRICHED URANIUM
K CODES
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
RADIOACTIVE WASTES
VALIDATION
Validation