Optimizing the source of radioactive waste generation at a nuclear research facility based on properly selected material for experimental devices

Optimization of radioactive waste generation sources is seen as a most important factor supporting sustainable operation of research nuclear reactors and contributing to lower radiation exposure of personnel. Based on a predictive assessment and experimental data, steel 20X13 was selected as a structural material for experimental devices. Its composition contributes to lower induced activity during irradiation in comparison with the samples made of steel 12X18N10T used widely at the present time. The study evaluates the composition and activity of radionuclides in the irradiated steel samples and calculates the changes in the induced activity of the samples over time. It forecasts the expected dose rate from the experimental device model and the one on the surface of the NZK‑150-1.5P container. Production of devices subject to irradiation from steel 20X13 is expected to reduce personnel exposure during product fragmentation by two times, shorten the cooling time before they can be further used after their irradiation in the core, as well as the storage time for spent products before they can be shipped safety for subsequent conditioning and final disposal.

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Publication Details

Journal
Radioactive waste
Published
2025-01-01
DOI
https://doi.org/10.25283/2587-9707-2025-2-18-26
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
Field-Weighted Citation Impact
0.00

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article

Optimizing the source of radioactive waste generation at a nuclear research facility based on properly selected material for experimental devices

А. А. Екидин, M. Zhukovsky
Radioactive waste
Graphite, nuclear technology, radiation studies
article

Optimizing the source of radioactive waste generation at a nuclear research facility based on properly selected material for experimental devices

А. А. Екидин, M. Zhukovsky
article en

Abstract

Optimization of radioactive waste generation sources is seen as a most important factor supporting sustainable operation of research nuclear reactors and contributing to lower radiation exposure of personnel. Based on a predictive assessment and experimental data, steel 20X13 was selected as a structural material for experimental devices. Its composition contributes to lower induced activity during irradiation in comparison with the samples made of steel 12X18N10T used widely at the present time. The study evaluates the composition and activity of radionuclides in the irradiated steel samples and calculates the changes in the induced activity of the samples over time. It forecasts the expected dose rate from the experimental device model and the one on the surface of the NZK‑150-1.5P container. Production of devices subject to irradiation from steel 20X13 is expected to reduce personnel exposure during product fragmentation by two times, shorten the cooling time before they can be further used after their irradiation in the core, as well as the storage time for spent products before they can be shipped safety for subsequent conditioning and final disposal.

Radioactive wasteVol. 31(2)
Ministry of Education and Science of the Russian Federation
Openalex Percentile: Top 89%
Graphite, nuclear technology, radiation studies
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