Measurement of the Thermal Neutron Fluence Rate in the Instrument Thimble 11 Position in the Advanced Test Reactor Critical

The Advanced Test Reactor Critical (ATRC) is a full-scale replica of the Advanced Test Reactor (ATR) core, utilized primarily for evaluating experiment impacts on power distribution. This study focuses on neutron fluence measurements within Instrument Thimble 11 (IT-11) by means of radiometric activation of passive dosimetry packages. These packages contained indium and gold thin foils as well as gold, cobalt, and nickel wire utilized during the 23-3 and 23-4 ATRC irradiations within IT-11 to evaluate the neutron field present within the test position. Measurement variances were observed between the various dosimetry methods, likely due to self-shielding effects in dosimetry foils and potential epithermal neutron contributions. Future work includes refining self-shielding corrections, exploring neutron field directionality, and developing epithermal corrections to resolve discrepancies. The findings aim to establish a more accessible and affordable test platform for nuclear instrumentation development and testing at the ATR facility.

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Publication Details

Journal
EPJ Web of Conferences
Published
2025-01-01
DOI
https://doi.org/10.1051/epjconf/202533804034
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

Measurement of the Thermal Neutron Fluence Rate in the Instrument Thimble 11 Position in the Advanced Test Reactor Critical

Kelly McCary, Michael Reichenberger, Dani Ottaway
EPJ Web of Conferences
Nuclear reactor physics and engineering
article

Measurement of the Thermal Neutron Fluence Rate in the Instrument Thimble 11 Position in the Advanced Test Reactor Critical

Kelly McCary, Michael Reichenberger, Dani Ottaway
article en

Abstract

The Advanced Test Reactor Critical (ATRC) is a full-scale replica of the Advanced Test Reactor (ATR) core, utilized primarily for evaluating experiment impacts on power distribution. This study focuses on neutron fluence measurements within Instrument Thimble 11 (IT-11) by means of radiometric activation of passive dosimetry packages. These packages contained indium and gold thin foils as well as gold, cobalt, and nickel wire utilized during the 23-3 and 23-4 ATRC irradiations within IT-11 to evaluate the neutron field present within the test position. Measurement variances were observed between the various dosimetry methods, likely due to self-shielding effects in dosimetry foils and potential epithermal neutron contributions. Future work includes refining self-shielding corrections, exploring neutron field directionality, and developing epithermal corrections to resolve discrepancies. The findings aim to establish a more accessible and affordable test platform for nuclear instrumentation development and testing at the ATR facility.

EPJ Web of ConferencesVol. 338
Idaho National Laboratory (US), National Measurement Laboratory (AU)
Openalex Percentile: Top 56%
Nuclear reactor physics and engineering
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