NJOY: a comprehensive ENDF/B processing system
Conference
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OSTI ID:6819934
NJOY is the successor to the MINX code. It provides an efficient and accurate capability for processing ENDF/B-IV and -V data for use in fast reactor, thermal reactor, fusion reactor, shielding, and weapons analysis. NJOY produces neutron cross sections and group-to-group scattering matrices, heat production cross sections, photon production matrices, photon interaction cross sections and group-to-group matrices, delayed neutron spectra, thermal scattering cross sections and matrices, and cross-section covariances. Detailed pointwise cross sections, heating KERMA factors, thermal cross sections, and energy-to-energy thermal matrices are also available for plotting and Monte Carlo applications. NJOY currently processes all types of data on ENDF/B except for the decay chain and fission product yield files. NJOY provides output in the CCCC ISOTXS, BRKOXS, and DLAYXS formats, in DTF/ANISN format, and in a new comprehensive format called MATXS. Other important features of NJOY include free-format input, efficient binary I/O, dynamic storage allocation, an extremely modular structure, an accurate center-of-mass Gaussian integration for two-body scattering, and a flux calculator that makes it possible to compute accurate self-shielded cross sections when wide and intermediate-width resonance effects are important. NJOY is a single, integrated, efficient system that produces almost all of the basic cross sections required for multigroup methods of nuclear analysis. 3 figures, 4 tables.
- Research Organization:
- Los Alamos Scientific Lab., N.Mex. (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6819934
- Report Number(s):
- LA-UR-78-771; CONF-780334-4
- 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]
LINX and BINX: CCCC utility codes for the MINX multigroup processing code
CINX: Collapsed Interpretation of Nuclear X sections
Technical Report
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·
OSTI ID:6423047
LINX and BINX: CCCC utility codes for the MINX multigroup processing code
Technical Report
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Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:4033045
CINX: Collapsed Interpretation of Nuclear X sections
Technical Report
·
Sun Feb 29 23:00:00 EST 1976
·
OSTI ID:7278883
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
654002 -- Radiation & Shielding Physics-- Shielding Calculations & Experiments-- (-1987)
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYONS
COMPUTER CODES
CROSS SECTIONS
ELEMENTARY PARTICLES
ENERGY SPECTRA
EPITHERMAL REACTORS
FAST NEUTRONS
FAST REACTORS
FERMIONS
HADRONS
KERMA
MULTIGROUP THEORY
N CODES
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEAR WEAPONS
NUCLEONS
RADIATION TRANSPORT
REACTORS
SCATTERING
SELF-SHIELDING
SHIELDING
SPECTRA
THERMAL NEUTRONS
THERMAL REACTORS
THERMONUCLEAR REACTORS
TRANSPORT THEORY
WEAPONS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
654002 -- Radiation & Shielding Physics-- Shielding Calculations & Experiments-- (-1987)
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYONS
COMPUTER CODES
CROSS SECTIONS
ELEMENTARY PARTICLES
ENERGY SPECTRA
EPITHERMAL REACTORS
FAST NEUTRONS
FAST REACTORS
FERMIONS
HADRONS
KERMA
MULTIGROUP THEORY
N CODES
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
NEUTRONS
NUCLEAR WEAPONS
NUCLEONS
RADIATION TRANSPORT
REACTORS
SCATTERING
SELF-SHIELDING
SHIELDING
SPECTRA
THERMAL NEUTRONS
THERMAL REACTORS
THERMONUCLEAR REACTORS
TRANSPORT THEORY
WEAPONS