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

doi 10.2172/7218408

Full Text

Abstract

Available in

Date

January 12, 1977

Authors

D.E. Cullen

Publisher

Office of Scientific and Technical Information (OSTI)

Related search

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

1976

English

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]

1979

English

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]

1975

English

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

1976

English

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

1977

English

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

1972

English

EVALUATION OF THE $Sup 239$Pu CROSS SECTIONS IN THE RESONANCE REGION FOR THE ENDF/B VERSION III DATA FILE.

1971

English

Second Version of Japanese Evaluated Nuclear Data Library (JENDL-2)

Journal of Nuclear Science and Technology

English

Program RECENT (Version 79-1): Reconstruction of Energy-Dependent Neutron Cross Sections From Resonance Parameters in the ENDF/B Format. [In FORTRAN IV for CDC-7600 and Cray-1]

1979

English

Amanote Research

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

Full Text

Abstract

Date

Authors

Publisher

Related search

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 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. 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. ECSIL: A System for Storage, Retrieval, and Display of Experimental Neutron Data

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 13. An Atlas of Unresolved Neutron Resonance Parameters.

EVALUATION OF THE $Sup 239$Pu CROSS SECTIONS IN THE RESONANCE REGION FOR THE ENDF/B VERSION III DATA FILE.

Second Version of Japanese Evaluated Nuclear Data Library (JENDL-2)

Program RECENT (Version 79-1): Reconstruction of Energy-Dependent Neutron Cross Sections From Resonance Parameters in the ENDF/B Format. [In FORTRAN IV for CDC-7600 and Cray-1]