Measured neutron flux parameters in the USGS TRIGA MARK I reactor

M. A. Koehl; R. S. Rundberg; J. C. Braley

doi:10.1007/s10967-015-4058-9

Measured neutron flux parameters in the USGS TRIGA MARK I reactor

M. A. Koehl, R. S. Rundberg, J. C. Braley

Research output: Contribution to journal › Article › peer-review

11 Scopus citations

Abstract

Using the Westcott convention, the Westcott flux, φw; modified spectral index, (Formula presented.) neutron temperature, T_n; and gold-based cadmium ratios were determined for various sampling positions in the U.S. Geological Survey (USGS) Training, Research, Isotopes, General Atomic (TRIGA) Mark I reactor. Westcott parameters were determined by a bare multi-monitor method. Thermal-neutron temperature measurements were made using lutetium foils. The differential neutron energy spectrum measurement was obtained using the computer iterative code SAND-II-SNL. Measurement of the neutron spectrum has resulted in a better knowledge of the reactor core and will improve predictive radioisotope production calculations necessary for neutron activation analysis and medical isotope production.

Original language	English
Pages (from-to)	31-38
Number of pages	8
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume	306
Issue number	1
DOIs	https://doi.org/10.1007/s10967-015-4058-9
State	Published - Oct 10 2015
Externally published	Yes

Keywords

Neutron spectrum characterization
SAND-II-SNL
Spectrum unfolding
TRIGA reactor
Westcott convention

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10.1007/s10967-015-4058-9

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title = "Measured neutron flux parameters in the USGS TRIGA MARK I reactor",

abstract = "Using the Westcott convention, the Westcott flux, φw; modified spectral index, (Formula presented.) neutron temperature, Tn; and gold-based cadmium ratios were determined for various sampling positions in the U.S. Geological Survey (USGS) Training, Research, Isotopes, General Atomic (TRIGA) Mark I reactor. Westcott parameters were determined by a bare multi-monitor method. Thermal-neutron temperature measurements were made using lutetium foils. The differential neutron energy spectrum measurement was obtained using the computer iterative code SAND-II-SNL. Measurement of the neutron spectrum has resulted in a better knowledge of the reactor core and will improve predictive radioisotope production calculations necessary for neutron activation analysis and medical isotope production.",

keywords = "Neutron spectrum characterization, SAND-II-SNL, Spectrum unfolding, TRIGA reactor, Westcott convention",

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note = "Publisher Copyright: {\textcopyright} 2015, Akad{\'e}miai Kiad{\'o}, Budapest, Hungary.",

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doi = "10.1007/s10967-015-4058-9",

language = "English",

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AU - Koehl, M. A.

AU - Rundberg, R. S.

AU - Braley, J. C.

PY - 2015/10/10

Y1 - 2015/10/10

N2 - Using the Westcott convention, the Westcott flux, φw; modified spectral index, (Formula presented.) neutron temperature, Tn; and gold-based cadmium ratios were determined for various sampling positions in the U.S. Geological Survey (USGS) Training, Research, Isotopes, General Atomic (TRIGA) Mark I reactor. Westcott parameters were determined by a bare multi-monitor method. Thermal-neutron temperature measurements were made using lutetium foils. The differential neutron energy spectrum measurement was obtained using the computer iterative code SAND-II-SNL. Measurement of the neutron spectrum has resulted in a better knowledge of the reactor core and will improve predictive radioisotope production calculations necessary for neutron activation analysis and medical isotope production.

AB - Using the Westcott convention, the Westcott flux, φw; modified spectral index, (Formula presented.) neutron temperature, Tn; and gold-based cadmium ratios were determined for various sampling positions in the U.S. Geological Survey (USGS) Training, Research, Isotopes, General Atomic (TRIGA) Mark I reactor. Westcott parameters were determined by a bare multi-monitor method. Thermal-neutron temperature measurements were made using lutetium foils. The differential neutron energy spectrum measurement was obtained using the computer iterative code SAND-II-SNL. Measurement of the neutron spectrum has resulted in a better knowledge of the reactor core and will improve predictive radioisotope production calculations necessary for neutron activation analysis and medical isotope production.

KW - Neutron spectrum characterization

KW - SAND-II-SNL

KW - Spectrum unfolding

KW - TRIGA reactor

KW - Westcott convention

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DO - 10.1007/s10967-015-4058-9

M3 - Article

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VL - 306

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EP - 38

JO - Journal of Radioanalytical and Nuclear Chemistry

JF - Journal of Radioanalytical and Nuclear Chemistry

IS - 1

ER -

Measured neutron flux parameters in the USGS TRIGA MARK I reactor

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Keywords

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