(PDF) Integrated System for Production of Neutronics and

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

doi 10.2172/4564912

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Date

January 1, 1972

Authors

M. Gyulassy

S.T. Perkins

Publisher

Office of Scientific and Technical Information (OSTI)

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

doi 10.2172/4564912

Full Text

Abstract

Date

Authors

Publisher

Related search

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

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

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. 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 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]

A Short History of ENDF/B Unresolved Resonance Parameters

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