Generation and Testing of the ENDF/B-VI Continuous-Energy Cross-Section Library for Use with Continuous-Energy Versions of KENO
Conference
·
OSTI ID:931781
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
KENO V.a and KENO-VI are Monte Carlo codes that solve the multigroup form of the Boltzmann transport equation. These codes are part of the SCALE system of codes and are used for performing criticality calculations of systems with fissionable material. In general, continuous-energy Monte Carlo methods are preferred because such an approach avoids many of the assumptions inherent in the multigroup treatment. On the other hand, continuous-energy treatment is much more demanding in terms of computer storage space for data, memory requirements, and calculation speed. Continuous-energy versions of KENO V.a and KENO-VI have been created and are being extensively tested. Generation of ENDF/B-VI continuous-energy cross sections is explained, and the results of the validation and verification of the codes and the data are presented.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 931781
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
97 MATHEMATICS AND COMPUTING
BOLTZMANN EQUATION
COMPUTER CODES
COMPUTERS
CRITICALITY
CROSS SECTIONS
Criticality Calculations
Explanations
FISSIONABLE MATERIALS
KENO V.a
KENO-VI
MONTE CARLO METHOD
Monte Carlo Codes
Multigroup Boltzmann Transport Equation Solution
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
SAFETY
SCALE System
STORAGE
TESTING
VALIDATION
VERIFICATION
Validation
Verification
97 MATHEMATICS AND COMPUTING
BOLTZMANN EQUATION
COMPUTER CODES
COMPUTERS
CRITICALITY
CROSS SECTIONS
Criticality Calculations
Explanations
FISSIONABLE MATERIALS
KENO V.a
KENO-VI
MONTE CARLO METHOD
Monte Carlo Codes
Multigroup Boltzmann Transport Equation Solution
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
SAFETY
SCALE System
STORAGE
TESTING
VALIDATION
VERIFICATION
Validation
Verification