ENDF/B-IV, and V Cross Section Libraries for Thermal Power Reactor Analysis
Conference
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OSTI ID:5765855
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States). University of California
The NJOY processing system was used to produce thermal reactor cross-section libraries from ENDF/B-IV, and -V evaluations for the fuel cycle codes EPRI-CELL and EPRI-CPM, for the continuous-energy Monte Carlo code MCNP, and for the Los Alamos discrete-ordinates transport codes. This consistent data source allowed the approximate methods (equivalence theory, B1, integral transport, PL-SN) to be compared with accurate Monte Carlo results. So far, this has resulted in improved methods for space-and-energy self-shielding in the resonance range (e.g., the NJOY flux calculator, epithermal disadvantage factors for EPRI-CELL, shielded elastic removal), it has shown why the newest ENDF-based libraries initially gave results worse than the old libraries, and it has pointed out problems for future study such as resonance interference effects at high burnup. Finally, the results are compared to various criticality benchmarks to evaluate the performance of ENDF/B-V for thermal reactor analysis and to establish the biases introduced by the approximate methods used in the fuel cycle codes.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States). University of California
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5765855
- Report Number(s):
- LA-UR--79-2897; CONF-791058-17
- Country of Publication:
- United States
- Language:
- English
Similar Records
Processing and testing ENDF/B-VI with NJOY and TRANSX
NJOY; neutron and photon crosssections from ENDF/B. [CDC7600; American National Standard X3. 9-1966 FORTRAN language is used with a few exceptions, such as CDC overlay commands, mixed-mode arithmetic, and expressions as array indices. Machine-dependent functions such as timing, input-output, and character manipulation are isolated in special subroutines. Changes required for IBM implementation are denoted by 'CIBM' comment cards. Some loops have been rearranged to facilitate vectorization]
MCNP Calculations for Criticality Safety Benchmarks with ENDF/B-V and ENDF/B-VI Libraries
Conference
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Sun May 01 00:00:00 EDT 1994
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OSTI ID:10149774
NJOY; neutron and photon crosssections from ENDF/B. [CDC7600; American National Standard X3. 9-1966 FORTRAN language is used with a few exceptions, such as CDC overlay commands, mixed-mode arithmetic, and expressions as array indices. Machine-dependent functions such as timing, input-output, and character manipulation are isolated in special subroutines. Changes required for IBM implementation are denoted by 'CIBM' comment cards. Some loops have been rearranged to facilitate vectorization]
Technical Report
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OSTI ID:6423047
MCNP Calculations for Criticality Safety Benchmarks with ENDF/B-V and ENDF/B-VI Libraries
Conference
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Sun Sep 17 00:00:00 EDT 1995
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OSTI ID:97187
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BARYON REACTIONS
CROSS SECTIONS
ENDF
EVALUATION
EXPERIMENTAL REACTORS
FUEL CYCLE
HADRON REACTIONS
Monte Carlo Code MCNP
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON TRANSPORT
NJOY
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
Nuclear Criticality Safety Program (NCSP)
RADIATION TRANSPORT
REACTORS
RESEARCH AND TEST REACTORS
THERMAL REACTORS
ZERO POWER REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BARYON REACTIONS
CROSS SECTIONS
ENDF
EVALUATION
EXPERIMENTAL REACTORS
FUEL CYCLE
HADRON REACTIONS
Monte Carlo Code MCNP
NEUTRAL-PARTICLE TRANSPORT
NEUTRON REACTIONS
NEUTRON TRANSPORT
NJOY
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
Nuclear Criticality Safety Program (NCSP)
RADIATION TRANSPORT
REACTORS
RESEARCH AND TEST REACTORS
THERMAL REACTORS
ZERO POWER REACTORS