Calculation of the Thermal Neutron Scattering Cross-Section of Solids Using OCLIMAX

Author:

Cheng Y. Q.1ORCID,Ramirez-Cuesta A. J.1ORCID

Affiliation:

1. Neutron Scattering Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831, United States

Funder

Basic Energy Sciences

Publisher

American Chemical Society (ACS)

Subject

Physical and Theoretical Chemistry,Computer Science Applications

Reference47 articles.

1. Neutron scattering lengths and cross sections

2. Slow-neutron scattering by molecular gases: A synthetic scattering function

3. Hawari, A. I.; Al-Qasir, I. I.; Gillette, V.; Wehring, B.; Zhou, T. In Ab Initio Generation of Thermal Neutron Scattering Cross Sections, Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems—Global Developments; 2004.

4. Modern Techniques for Inelastic Thermal Neutron Scattering Analysis

5. Hawari, A. I.; Zhu, Y.; Wormald, J. L.; Manring, C. A.; Sorrell, N. C. In Thermal Neutron Scattering Law Data Evaluations for Nuclear Technology Applications, M&C 2017—International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering; 2017.

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