Methods for Processing ENDF/B-VII with NJOY
The NJOY Nuclear Data Processing System is widely used to convert evaluations in the Evaluated Nuclear Data Files (ENDF) format into forms useful for practical applications such as fission and fusion reactor analysis, stockpile stewardship calculations, criticality safety, radiation shielding, nuclear waste management, nuclear medicine procedures, and more. This paper provides a description of the system's capabilities, summary descriptions of the methods used, and information on how to use the code to process the modern evaluated nuclear data files from ENDF/B-VII. It begins with the generation of pointwise libraries, including reaction and resonance reconstruction, Doppler broadening, radiation heating and damage, thermal scattering data, unresolved resonance data, and gas production. It then reviews the production of libraries for the continuous-energy Monte Carlo code MCNP, multigroup neutron, photon, and particle cross sections and matrices, and photon interaction data. The generation of uncertainty information for ENDF data is discussed, including new capabilities for calculating covariances of resonance data, angular distributions, energy distributions, and radioactive nuclide production. NJOY's ability to prepare thermal scattering data evaluations for bound moderators (which was used during the preparation of the ENDF/B-VII library) is described. The strong plotting capabilities of NJOY are summarized. Many examples of black and white and color Postscript plots are included throughout the paper. The capabilities of NJOY to output multigroup data in several different formats to suit various applications is reviewed. Finally, a section is included that summarizes the history of the development of the NJOY system over the last 37 years.
- OSTI ID:
- 21499796
- Journal Information:
- Nuclear Data Sheets, Journal Name: Nuclear Data Sheets Journal Issue: 12 Vol. 111; ISSN NDTSBA; ISSN 0090-3752
- Country of Publication:
- United States
- Language:
- English
Similar Records
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]
NJOY2016
Related Subjects
ANGULAR DISTRIBUTION
BARYONS
BOSONS
CALCULATION METHODS
CRITICALITY
CROSS SECTIONS
DATA PROCESSING
DISTRIBUTION
DOPPLER BROADENING
ELEMENTARY PARTICLES
ENERGY SPECTRA
EVALUATION
FERMIONS
FISSION
HADRONS
HEATING
LINE BROADENING
MANAGEMENT
MASSLESS PARTICLES
MEDICINE
MONTE CARLO METHOD
MULTIGROUP THEORY
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEAR DATA COLLECTIONS
NUCLEAR MEDICINE
NUCLEAR REACTIONS
NUCLEONS
PHOTONS
PROCESSING
RADIATION HEATING
RADIOACTIVE WASTE MANAGEMENT
RESONANCE
SAFETY
SHIELDING
SPECTRA
THERMONUCLEAR REACTORS
TRANSPORT THEORY
WASTE MANAGEMENT