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 ·

OSTI ID:6423047

Fowler, T B; Tobias, M L; Fox, J N; Lawler, B E; Koppel, J U; Triplett, J R; Lynn, L L; Waldman, L A; Goldberg, I; Greebler, P; Kelley, M D; Davis, R A; Keck, C E; Redfield, J A; Murphy,; Boicourt, R M

The NJOY nuclear data processing system is a comprehensive set of processing modules for producing pointwise and multigroup cross sections for neutron and photon transport calculations from ENDF/B-IV and -V evaluated nuclear data. Each module performs a well-defined processing task. RECONR reconstructs pointwise (energy-dependent) cross sections from ENDF/B resonance parameters and interpolation schemes. BROADR Doppler-broadens and thins pointwise cross sections. UNRESR computes effective self-shielded pointwise cross sections in the unresolved-resonance region. HEATR generates pointwise heat production cross sections (kerma factors) and radiation-damage-energy production cross sections. THERMR produces incoherent inelastic energy-to-energy matrices for free or bound scatterers, coherent elastic cross sections for hexagonal materials, and incoherent elastic cross sections. GROUPR generates self-shielded multigroup cross sections, group-to-group neutron scattering matrices, and photon production matrices from pointwise input. GAMINR calculates multigroup photon interaction cross sections and kerma factors and group-to-group photon scattering matrices. ERRORR produces multigroup covariance matrices from ENDF/B uncertainties. COVR reads the ERRORR output and performs covariance plotting and output formatting. DTFR formats multigroup data for use in transport codes, such as DTF4 and ANISN. CCCCR formats multigroup data for the CCCC standard interface files ISOTXS, BRKOXS, and DLAYXS. MATXSR formats multigroup data for the cross section interface file MATXS. MODER changes ENDF/B and ENDF-like NJOY interface files from formatted decimal format (BCD or ASCII) into a blocked binary format and back. The ACER module prepares libraries for the Los Alamos continuous-energy Monte Carlo code MCNP, and POWR prepares libraries for the proprietary EPRI-CELL and EPRI-CPM power reactor fuel-cycle codes.

• Research Organization: Los Alamos National Lab., NM (USA)
• OSTI ID: 6423047
• Report Number(s): ANL/NESC-883; ON: DE83048883
• Country of Publication: United States
• Language: English

Related Subjects

654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
COMPUTER CODES
CROSS SECTIONS
DOPPLER BROADENING
ELEMENTARY PARTICLES
HADRON REACTIONS
LINE BROADENING
MASSLESS PARTICLES
MULTIGROUP THEORY
N CODES
NEUTRON REACTIONS
NEUTRON TRANSPORT THEORY
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHOTONS
SCATTERING
SELF-SHIELDING
SHIELDING
TRANSPORT THEORY