Issue |
EPJ Web Conf.
Volume 308, 2024
ISRD 17 – International Symposium on Reactor Dosimetry (Part II)
|
|
---|---|---|
Article Number | 06004 | |
Number of page(s) | 11 | |
Section | Dosimetry in Test and Research Reactors | |
DOI | https://doi.org/10.1051/epjconf/202430806004 | |
Published online | 11 November 2024 |
https://doi.org/10.1051/epjconf/202430806004
Fast and thermal neutron spectrum dosimetry measurements in the Advanced Test Reactor large-B and small-l positions following the sixth core internals change-out
1 Idaho National Laboratory, Energy and Environment Science and Technology, 1955 N Fremont Ave, Idaho Falls, ID 83415, USA
2 Idaho National Laboratory, Advanced Test Reactor, 1955 N Fremont Ave, Idaho Falls, ID 83415, USA
3 Idaho National Laboratory, Nuclear Science and Technology, 1955 N Fremont Ave, Idaho Falls, ID 83415, USA
* Corresponding author: michael.reichenberger@inl.gov
Published online: 11 November 2024
The Advanced Test Reactor (ATR) has a wide variety of irradiation positions that have had experiments that were developed by users from around the world. Most experiment irradiations rely on thoroughly benchmarked numerical models. However, some irradiation positions in ATR are not as well- characterized and are complicated by spectral perturbations from control cylinder orientation. The “small I” and “large-B” irradiation positions are located nearby control cylinders and suffer from these flux perturbations from control cylinder orientations that change during an irradiation cycle to maintain the desired core power distribution. Models predicted that these types of position would exhibit both spectral shifts and amplitude changes in neutron flux, but few measurements have been conducted to benchmark these predictions. Recently, requalification testing was performed to confirm the operational readiness of the ATR following the completion of the Core Internals Change-out (CIC). These tests provided a unique opportunity to validate the analytical methods used to simulate the ATR because nearly all components in the reactor were in a clean as-built state, significantly reducing modelling uncertainties. One subset of the testing included characterization of the fast and thermal neutron flux in the “small-I” and “large-B” positions using silver, cobalt, and nickel neutron dosimetry. In contrast to typical irradiation cycles, the control cylinders were held in position during the post-CIC nuclear testing. The specific activity of these dosimeter wires was measured following two low-power tests with different control cylinder positions.
© The Authors, published by EDP Sciences, 2024
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