| Issue |
EPJ Web Conf.
Volume 338, 2025
ANIMMA 2025 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
|
|
|---|---|---|
| Article Number | 04034 | |
| Number of page(s) | 4 | |
| Section | Research Reactors and Particle Accelerators | |
| DOI | https://doi.org/10.1051/epjconf/202533804034 | |
| Published online | 06 November 2025 | |
https://doi.org/10.1051/epjconf/202533804034
Measurement of the Thermal Neutron Fluence Rate in the Instrument Thimble 11 Position in the Advanced Test Reactor Critical
Radiation Measurement Laboratory, Idaho National Laboratory, USA
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Published online: 6 November 2025
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.
Key words: Advanced Test Reactor Critical / ATRC / Neutron Dosimetry / Instrument Thimble 11 / IT-11 / Thermal Neutron Column
© The Authors, published by EDP Sciences, 2025
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