Integrated System for Production of Neutronics and Photonics Calculational Constants. Volume 5, Revision 1. CLYDE, a Code for the Production of Calculational Constants From Nuclear Data. [For CDC-7600 Computer]

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September 30, 1975

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Office of Scientific and Technical Information (OSTI)

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Integrated System for Production of Neutronics and Photonics Calculational Constants. Volume 5, Revision 1. CLYDE, a Code for the Production of Calculational Constants From Nuclear Data. [For CDC-7600 Computer]

Full Text

Abstract

Date

Authors

Publisher

Related search

Integrated System for Production of Neutronics and Photonics Calculational Constants. Volume 13. An Atlas of Unresolved Neutron Resonance Parameters.

Integrated System for Production of Neutronics and Photonics Calculational Constants. ECSIL: A System for Storage, Retrieval, and Display of Experimental Neutron Data

Integrated System for Production of Neutronics and Photonics Calculational Constants. Volume 21, Part C, Program SIGMAL (Version 79-1): Doppler-Broaden Evaluated Cross Sections in the Livermore-Evaluated Nuclear Data Library (ENDL) Format. [In FORTRAN IV for CDC 7600]

Integrated System for Production of Neutronics and Photonics Calculational Constants. Program LINEAR (Version 77-1): Linearize Data in the Evaluated Nuclear Data File/Version B (ENDF/B) Format

Integrated System for Production of Neutronics and Photonics Calculational Constants. Volume 15, Part D. The LLL Evaluated Nuclear Data Library (ENDL): Descriptions of Individual Evaluations for Z = 90 to 98

Integrated System for Production of Neutronics and Photonics Calculational Constants. Volume 15, Part C. The LLL Evaluated Nuclear Data Library (ENDL): Translation of ENDL Neutron-Induced Interaction Data Into the ENDF/B Format

SOC Code: Lagrangian, Finite-Difference Calculational Technique in One-Dimensional Symmetry. [In Modified Fortran IV for CDC 7600]

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