Development of the CPXSD Methodology for Generation of Fine-Group Libraries for Shielding Applications-Reference-Cited by-同舟云学术

Development of the CPXSD Methodology for Generation of Fine-Group Libraries for Shielding Applications

Published:2005-01 Issue:1 Volume:149 Page:51-64
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Alpan F. Arzu¹,Haghighat Alireza²

Affiliation:

1. The Pennsylvania State University, Mechanical and Nuclear Engineering Department 127 Reber Building, University Park, Pennsylvania 16802

2. University of Florida, Nuclear and Radiological Engineering Department 202 Nuclear Sciences Building, Gainesville, Florida 32611

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE04-23

Reference17 articles.

1. Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence

2. “Neutron and Gamma-Ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants,” ANSI/ANS-6.1.2-1989, American Nuclear Society (1989).

3. R. E. MacFARLANE and D. E. MUIR, “NJOY94.61: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data,” PSR-355, Los Alamos National Laboratory (Dec. 1996).

4. “AMPX-77: Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B,” PSR-315, Oak Ridge National Laboratory (Oct. 1992).

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