UNRESR computes effective self-shielded pointwise cross sections in the unresolved-resonance region. BROADR Doppler-broadens and thins pointwise cross sections. RECONR reconstructs pointwise (energy-dependent) cross sections from ENDF/B resonance parameters and interpolation schemes. Each module performs a well-defined processing task. 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. NJOY is a single, integrated, efficient system that produces almost all of the basic cross sections required for multigroup methods of nuclear analysis. 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 provides output in the CCCC ISOTXS, BRKOXS, and DLAYXS formats, in DTF/ANISN format, and in a new comprehensive format called MATXS. NJOY currently processes all types of data on more » ENDF/B except for the decay chain and fission product yield files. 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 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. 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. NESC execution of the CDC7600 sample problem required about 127,000 (octal) words of storage. NESC tested this problem without overlay using 610K bytes on an IBM370/195. The 50-group library problem with overlay on the IBM370 requires approximately 330K bytes of memory. Fine-group energy boundaries, Legendre expansion order, gross spectral shape component in the Bondarenko (reference 9) flux model, temperatures, and dilutions can all be user-specified.CDC7600 IBM370 more » FORTRAN IV (H compiler) and BAL (IBM370), FORTRAN IV (RUN or FTN compiler) and COMPASS (CDC7600) OS/370 (IBM370), SCOPE (CDC7600) Storage requirements depend on characteristics of the problem. MINX incorporates and improves upon the resonance capabilities of existing codes such as ETOX (reference 5) and ENDRUN (reference 6) and the high-order group-to-group transfer matrices of SUPERTOG (reference 7) and ETOG (reference 8). Its primary purpose is to generate a pseudo-composition independent multigroup library for input to the SPHINX (reference 3) space-energy collapse program using CCCC-III (reference 4) standard interfaces. MINX calculates fine-group averaged infinitely-dilute cross sections and self-shielding factors from ENDF/B-IV (reference 2) data.
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