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Title: Calculation procedures for the analysis of integral experiments for fusion-reactor design

Abstract

The calculational models, nuclear data, and radiation transport codes that are used in the analysis of integral measurements of the transport of approx. 14 MeV neutrons through laminated slabs of materials typical of those found in fusion reactor shields are described. The two-dimensional discrete ordinates calculations to optimize the experimental configuration for reducing the neutron and gamma ray background levels and for obtaining an equivalent, reduced geometry of the calculational model to reduce computer core storage and running times are also presented. The equations and data to determine the energy-angle relations to neutrons produced in the reactions of 250 keV deuterons in a titanium-tritide target are given. The procedures used to collapse the 17ln-36..gamma.. VITAMIN C cross section data library to a 53n-21..gamma.. broad group library are described. Finally, a description of the computer code network used to obtain neutron and gamma ray energy spectra for comparison with measured data is included.

Authors:
; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
OSTI Identifier:
6309114
Report Number(s):
ORNL-5777
ON: DE81027626; TRN: 81-014848
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; SHIELDING; NEUTRON TRANSPORT; PHOTON TRANSPORT; THERMONUCLEAR REACTORS; COMPUTER CALCULATIONS; DISCRETE ORDINATE METHOD; ENERGY SPECTRA; GAMMA RADIATION; ELECTROMAGNETIC RADIATION; IONIZING RADIATIONS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; RADIATIONS; SPECTRA; 700209* - Fusion Power Plant Technology- Component Development & Materials Testing

Citation Formats

Santoro, R T, Barnes, J M, Alsmiller, Jr, R G, and Oblow, E M. Calculation procedures for the analysis of integral experiments for fusion-reactor design. United States: N. p., 1981. Web. doi:10.2172/6309114.
Santoro, R T, Barnes, J M, Alsmiller, Jr, R G, & Oblow, E M. Calculation procedures for the analysis of integral experiments for fusion-reactor design. United States. https://doi.org/10.2172/6309114
Santoro, R T, Barnes, J M, Alsmiller, Jr, R G, and Oblow, E M. 1981. "Calculation procedures for the analysis of integral experiments for fusion-reactor design". United States. https://doi.org/10.2172/6309114. https://www.osti.gov/servlets/purl/6309114.
@article{osti_6309114,
title = {Calculation procedures for the analysis of integral experiments for fusion-reactor design},
author = {Santoro, R T and Barnes, J M and Alsmiller, Jr, R G and Oblow, E M},
abstractNote = {The calculational models, nuclear data, and radiation transport codes that are used in the analysis of integral measurements of the transport of approx. 14 MeV neutrons through laminated slabs of materials typical of those found in fusion reactor shields are described. The two-dimensional discrete ordinates calculations to optimize the experimental configuration for reducing the neutron and gamma ray background levels and for obtaining an equivalent, reduced geometry of the calculational model to reduce computer core storage and running times are also presented. The equations and data to determine the energy-angle relations to neutrons produced in the reactions of 250 keV deuterons in a titanium-tritide target are given. The procedures used to collapse the 17ln-36..gamma.. VITAMIN C cross section data library to a 53n-21..gamma.. broad group library are described. Finally, a description of the computer code network used to obtain neutron and gamma ray energy spectra for comparison with measured data is included.},
doi = {10.2172/6309114},
url = {https://www.osti.gov/biblio/6309114}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jul 01 00:00:00 EDT 1981},
month = {Wed Jul 01 00:00:00 EDT 1981}
}