• 암석학회지
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• 제17권3호
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• pp.179-190
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• 2008

부산 금정구일대의 암석, 토양 및 토양가스 내 주요 환경방사성 핵종들($^{40}K$, $^{228}Ac$, $^{226}Ra$, $^{222}Rn$) 및 U의 분포 특성에 대하여 연구하였다. 연구지역의 화강암질 암석들에서 환경방사성 핵종들의 방사능은 $^{40}K$>토륨붕괴계열>우라늄붕괴계열 순으로 낮게 나타나 화강암질 암석에서 U에 비해 Th이 상대적으로 많이 부화됨을 잘 나타내고 있다. 그러나 암석 내 U 농도 및 $^{226}Ra$ and $^{228}Ac$ 방사능은 암석의 분화단계를 잘 반영하지 못하고 있다. 잔류토양 내 환경방사성 이 핵종들의 방사능과 U의 농도는 모암에 비해 높게 나타나며. 토양가스, 토양 및 암석에서 환경방사성 핵종들의 분포는 낮은 정의 상관관계를 보인다. 이러한 사실들은, 토양가스 및 토양에서 환경방사성 핵종들의 방사능은 모암에 의한 영향보다, 암석의 풍화작용과 토양형성작용 동안 이들 핵종들과 모핵종들의 용탈 및 흡착 등의 거동 특성에 의한 영향을 더 크게 받음을 시사한다.

• Nuclear Engineering and Technology
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• 제45권7호
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• pp.847-858
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• 2013

Since 2001, a series of five irradiation test campaigns for atomized U-Mo dispersion fuel rods, KOMO-1, -2, -3, -4, and -5, has been conducted at HANARO (Korea) in order to develop high performance low enriched uranium dispersion fuel for research reactors. The KOMO irradiation tests provided valuable information on the irradiation behavior of U-Mo fuel that results from the distinct fuel design and irradiation conditions of the rod fuel for HANARO. Full size U-Mo dispersion fuel rods of 4-5 $g-U/cm^3$ were irradiated at a maximum linear power of approximately 105 kW/m up to 85% of the initial U-235 depletion burnup without breakaway swelling or fuel cladding failure. Electron probe microanalyses of the irradiated samples showed localized distribution of the silicon that was added in the matrix during fuel fabrication and confirmed its beneficial effect on interaction layer growth during irradiation. The modifications of U-Mo fuel particles by the addition of a ternary alloying element (Ti or Zr), additional protective coatings (silicide or nitride), and the use of larger fuel particles resulted in significantly reduced interaction layers between fuel particles and Al.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2725-2732
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• 2020

This paper presents the neutronics benchmark analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS (Reaktor Serba Guna G.A. Siwabessy) calculated by the Serpent Monte Carlo code and the newly released ENDF/B-VIII.0 nuclear data library. RSG-GAS is a 30 MWth pool-type material testing research reactor loaded with plate-type low-enriched uranium fuel using light water as a coolant and moderator and beryllium as a reflector. Two groups of critical benchmark problems are derived on the basis of the criticality and control rod calibration experiments of the first core of RSG-GAS. The calculated results, such as the neutron effective multiplication factor (k) value and the control rod worth are compared with the experimental data. Moreover, additional calculated results, including the neutron spectra in the core, fission rate distribution, burnup calculation, sensitivity coefficients, and kinetics parameters of the first core will be compared with the previous nuclear data libraries (interlibrary comparison) such as ENDF/B-VII.1 and JENDL-4.0. The C/E values of ENDF/B-VIII.0 tend to be slightly higher compared with other nuclear data libraries. Furthermore, the neutron reaction cross-sections of ¹⁶O, ⁹Be, ²³⁵U, ²³⁸U, and S(𝛼,𝛽) of ¹H in H₂O from ENDF/B-VIII.0 have substantial updates; hence, the k sensitivities against these cross-section changes are relatively higher than other isotopes in RSG-GAS. Other important neutronics parameters such as kinetics parameters, control rod worth, and fission rate distribution are similar and consistent among the nuclear data libraries.