Negative / Null Result ReportOpen accessNuclear engineering. Atomic power
Min Ho Lee, Dong Wook Jerng, In Cheol Bang · 2023 · Nuclear Engineering and Technology
The temperature distribution of the reactor pool under natural circulation induced by the RVACS operation was experimentally studied. According to the Bo’ based similarity law, which could reproduce the temperature distribution of the working fluid under natural circulation, SINCRO-2D facility was designed based on the PGSFR. It was reduced to 1 : 25 in length scale, having water as a simulant of the sodium, which is the original working fluid. In general, temperature was stratified, however, effect of the natural circulation flow could be observed by the entrainment of the stratified temperat
View details →Negative / Null Result ReportOpen accessNuclear engineering. Atomic power
Jei Ha Lee, Cha Soon Kim, Soo Im Choi et al. · 2019 · Nuclear Engineering and Technology
Tritium is an important nuclide that must be monitored for radiation safety management. In this study, HTO was orally administered to rats at the level of 37 kBq (1 μCi) or 370 kBq (10 μCi) to examine tissue distribution and excretion levels. After sacrifice, wet and dry tissue samples were weighed and analyzed for tissue free-water tritium (TFWT) and organically bound tritium (OBT). The mean tissue concentrations of TFWT (OBT) were 30.9 (17.8) and 4.4 (8.1) Bq/g on days 7 and 13 at the 37 kBq level and 30.8 (64.6) Bq/g on day 17 at the 370 kBq level. To assess the cytogenetic damage due to tr
View details →Negative / Null Result ReportOpen accessNuclear engineering. Atomic power
Junhyuk Jang, Minsoo Lee, Gha-Young Kim et al. · 2025 · Nuclear Engineering and Technology
Copper oxidation at low temperatures below 140 °C and its effects on corrosive behavior in aerobic groundwater are investigated to estimate the intactness of canisters at early stages of disposal. The Cu coupon surface is covered by fine particles that form thin oxide layers after 30 d of oxidation; a thin Cu2O layer of thickness <100 nm is formed after oxidation at 40 °C; after oxidation at 140 °C, the Cu2O surface changes to a CuO layer of thickness <500 nm. The thickness of the Cu surface oxidized at 90 °C is between those of the surfaces oxidized at 40 and 140 °C. All Cu coupons exhibit si
View details →Negative / Null Result ReportOpen accessNuclear engineering. Atomic power
Jun Yeong Jo, Chi Bum Bahn, Hwasung Yeom · 2024 · Nuclear Engineering and Technology
The dissolved oxygen in a coolant can affect the oxidation properties of structural materials. A desirable oxide phase formation is achieved by manipulating the oxygen level in the coolant, which can mitigate structural material degradation in nuclear power plants. Therefore, the role of dissolved oxygen in the corrosion of structural materials in aqueous environments needs to be understood. In this study, a short-term corrosion test (up to 300 h) of Ferritic/Martensitic steels (F/M steels; FeCrW model alloys), namely, Fe12Cr1W, Fe9Cr1W, and Fe9Cr, in stagnant water at 360 °C was performed in
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