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Title: Graphical User Interface for Simplified Neutron Transport Calculations

Abstract

A number of codes perform simple photon physics calculations. The nuclear industry is lacking in similar tools to perform simplified neutron physics shielding calculations. With the increased importance of performing neutron calculations for homeland security applications and defense nuclear nonproliferation tasks, having an efficient method for performing simple neutron transport calculations becomes increasingly important. Codes such as Monte Carlo N-particle (MCNP) can perform the transport calculations; however, the technical details in setting up, running, and interpreting the required simulations are quite complex and typically go beyond the abilities of most users who need a simple answer to a neutron transport calculation. The work documented in this report resulted in the development of the NucWiz program, which can create an MCNP input file for a set of simple geometries, source, and detector configurations. The user selects source, shield, and tally configurations from a set of pre-defined lists, and the software creates a complete MCNP input file that can be optionally run and the results viewed inside NucWiz.

Authors:
;
Publication Date:
Research Org.:
Visual Editor Consultants
Sponsoring Org.:
USDOE Office of Environmental Management (EM), Acquisition and Project Management (EM-50)
OSTI Identifier:
1018953
Report Number(s):
DOE/SC0002321-1
DOE Contract Number:  
SC0002321
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 61 RADIATION PROTECTION AND DOSIMETRY; Shielding Neutron Transport

Citation Formats

Schwarz, Randolph, and Carter, Leland L. Graphical User Interface for Simplified Neutron Transport Calculations. United States: N. p., 2011. Web. doi:10.2172/1018953.
Schwarz, Randolph, & Carter, Leland L. Graphical User Interface for Simplified Neutron Transport Calculations. United States. doi:10.2172/1018953.
Schwarz, Randolph, and Carter, Leland L. Mon . "Graphical User Interface for Simplified Neutron Transport Calculations". United States. doi:10.2172/1018953. https://www.osti.gov/servlets/purl/1018953.
@article{osti_1018953,
title = {Graphical User Interface for Simplified Neutron Transport Calculations},
author = {Schwarz, Randolph and Carter, Leland L},
abstractNote = {A number of codes perform simple photon physics calculations. The nuclear industry is lacking in similar tools to perform simplified neutron physics shielding calculations. With the increased importance of performing neutron calculations for homeland security applications and defense nuclear nonproliferation tasks, having an efficient method for performing simple neutron transport calculations becomes increasingly important. Codes such as Monte Carlo N-particle (MCNP) can perform the transport calculations; however, the technical details in setting up, running, and interpreting the required simulations are quite complex and typically go beyond the abilities of most users who need a simple answer to a neutron transport calculation. The work documented in this report resulted in the development of the NucWiz program, which can create an MCNP input file for a set of simple geometries, source, and detector configurations. The user selects source, shield, and tally configurations from a set of pre-defined lists, and the software creates a complete MCNP input file that can be optionally run and the results viewed inside NucWiz.},
doi = {10.2172/1018953},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2011},
month = {7}
}