• Nuclear Engineering and Technology
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• 제2권4호
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• pp.273-278
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• 1970

국내에서 채광한 자연방사능광물의 분석의뢰를 계기로 이에 관심을 갖고 Uranium와Thorium 의 함유량을 원광으로부터 비파괴적이고 간단한 ${\gamma}$-선 분광법으로 측정 분석하여 보았다. Ge(Li) 측정기를 ${\gamma}$-선 분광에 이용한 결과는 재래식방법에 비하여 분석정도를 훨씬 높일 수 있었으며, 자연방사능측정법과 원자로중성자로 조사시킨 activation법으로 Uranium와 Thorium의 함유량을 분석하였던바 하나의 시료(인천에서 채광)에서는 약 0.5%의 Uranium, 또 다른 시료에서는 2%의 Th와 0.1%의 U이 포함되어 있음이 확인되었다. 우리가 처음 시도한 이 분석법은 경제적이고 간편.신속하게 분석할수 있어 핵연료물질조사에 널러 이용할 수 있음을 입증한다.

• 분석과학
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• 제10권5호
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• pp.307-314
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• 1997

지질시료 중의 U과 Th을 유도결합플라즈마 원자방출분광법으로 정량하기 위해 시료를 혼산으로 분해하고 TTA(thenoyltrifluoroacetone)와 TOA (tri-n-octylamine) 추출제를 이용하여 계통적으로 용매추출한 다음 HCl 용액으로 역추출하여 분리하였다. 표준암석 NIST SRM 278에 대한 분석결과는 NIST 및 다른 비파괴분석 결과와 비교하여 양호하였다. 알파선분광법으로 U과 Th의 자연방사성 동위원소를 측정하기 위해 추출분리한 각각을 음이온교환크로마토그래피로 정제하였다.

• Nuclear Engineering and Technology
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• 제12권2호
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• pp.106-110
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• 1980

옥천계 흑혈암(black shale) 및 모나자이트에 함유된 우라늄 및 토륨의 방사화 평형조건에 관하여 연구하였다. 이 연구의 결과로 감마선 계측에 의한 이들 원소의 분석법을제시할 수 있었으며 많은 수의 광물 시료분석이 손쉽게 되었다.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1560-1569
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• 2022

Liquid fueled molten salt reactors (MSRs) have seen renewed interest because of their inherent safety features, higher thermal efficiency and potential for efficient thorium utilisation for power generation. Thorium fluoride is one of the salts used in liquid fueled MSRs employing Th-U cycle. In the present study, ThF₄ was prepared by hydro-fluorination of ThO₂ using anhydrous HF gas. Process parameters viz. bed depth, hydrofluorination time and hydrofluorination temperature, were optimized for the preparation of ThF₄ in a static bed reactor setup. The products were characterized with X-Ray diffraction and experimental conditions for complete conversion to ThF₄ were established which also corroborated with the yield values. Hydrofluorination of ThO₂ at 450 ℃ for half an hour at a bed depth of 6 mm gave the best result, with a yield of about 99.36% ThF₄. No unconverted oxide or any other impurity was observed. Rietveld refinement was performed on the XRD data of this ThF₄, and Chi2 value of 3.54 indicated good agreement between observed and calculated profiles.

• Nuclear Engineering and Technology
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• 제41권6호
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• pp.867-874
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• 2009

Solubility of a radionuclide is important for defining the release source term of a radioactive waste in the safety and performance assessments of a radioactive waste repository. When the pH and redox potential of the KURT groundwater were changed by an electrical method, the concentrations of uranium and thorium released from $UO_2$(cr) and $ThO_2$(cr) at alkali pH(8.1 ${\sim}$ 11.4) and reducing potential (Eh < -0.2 V) conditions were less than $10^{-7}mole/L$. Unexpectedly, the concentration of tetravalent thorium is slightly higher than that of uranium at pH = 8.1 and Eh= -0.2 V conditions, and this difference may be due to the formation of hydroxide-carbonate complex ions. When $UO_2$(s) and $UO_2$(am, hyd.), and $ThO_2$(s) and $Th(OH)_4(am)$ were assumed as solubility limiting solid phases, the concentrations of uranium and thorium in the KURT groundwater calculated by the PHREEQC code were comparable to the experimental results. The dominating aqueous species of uranium and thorium were presumed as $UO_2(CO_3)_3^{4-}$ and $Th(OH)_3CO_3^-$ at pH = 8.1 ${\sim}$ 9.8, and $UO_2(OH)_3^-$ and $Th(OH)_4(aq)$ at pH = 11.4.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.52-57
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• 1998

In this paper, we performed a design study of a thorium fueled reactor according to the design concept of the Radkowsky Thorium Reactor (RTR) and evaluated its overall performance. To enhance its performance and alleviate its problems, we introduced a new metallic uranium fuel, uranium-zirconium hydride (U-Zr $H_{1.6}$), as a seed fuel. For comparison, typical ABB/CE-type PWR based on SYSTBM 80+ and standard RTR-type thorium reactor were also studied. From the results of performance analysis, we could ascertain advantages of RTR-type thorium fueled reactor in proliferation resistance, fuel cycle economics, and back-end fuel cycle. Also, we found that enhancement of proliferation resistance and safer operating conditions may be achieved by using the U-Zr $H_{l.6}$ fuel in the seed region without additional penalties in comparison with the standard RTR's U-Zr fuelr fuelel

• Nuclear Engineering and Technology
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• 제50권5호
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• pp.794-800
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• 2018

The proliferation resistance (PR) of Th/U and Th/Pu fuels used in CANada Deuterium Uranium for the deep geological repository was assessed by combining the multiattribute utility analysis proposed by Chirayath et al., 2015 with the transport model of radionuclides in the repository and comparing with that of the used natural U fuel case. It was found that there was no significant advantage for Th/U and Th/Pu fuels from the viewpoint of the PR in the repository. It was also found that the PR values for used nuclear fuels in the repository of Th/U, Th/Pu, and natural U was comparable with those for enrichment and reprocessing facilities in the pressurized water reactor (PWR) nuclear fuel cycle. On the other hand, the PR values considering the transport of radionuclides in the repository were found to be slightly smaller than those without their transport after the used nuclear fuels started dissolving after 1,000 years.

• Nuclear Engineering and Technology
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• 제6권2호
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• pp.80-88
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• 1974

Amiel의 지발중성자 계측법을 사용한 분석과정을 다소 수정하여 지질학적 시료중의 우라륨 및 토륨의 동시 정량을 시도하였다. 본 분석과정은 넓은 범위의 두원소의 함량비에서 정화하게 적용할 수 있었다. 개발과정중 수행한 세력사항을 기술하였으며 나아가 본 분석법을 평가하였던 바 우라늄의 감도는 0.1$\mu\textrm{g}$이하였고 토륨의 감도는 약 5$\mu\textrm{g}$이었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.21-26
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• 1997

Recently, thorium is receiving increasing attention as an important fertile material for the expanding nuclear power programs around the world. The superior nuclear and physical properties of thorium-based fuels could lead to very low fuel cycle cost and make thorium reactors economically attractive. In addition, the use of thorium in reactors would permit more efficient utilization of low cost uranium reserves and reduction nuclear wastes. In this work, the nuclear characteristics of a new type thorium fueled reactor (Radkowsky Thorium Reactor) consisting seed-blanket assemblies are addressed and compared with those typical assemblies of a PWR (CE type). Also, an assessment on several advantages of thorium fueled reactors is provided. All these results are based on the HELIOS code calculation.

• 대한화학회지
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• 제38권7호
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• pp.502-508
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• 1994

염의 농도가 큰 시료용액중에 미량으로 함유되어 있는 U(VI)과 Th(VI)을 액상크로마토그래피로 동시에 분리, 정량하였다. 약 2ml의 시료를 pH5.5의 0.11M ${\alpha}$-HIBA 용리액과 함께 C_{18}$ 역상농축컬럼에 통과시켜 U(VI)과 Th(VI)을 농축시켰으며, 농축된 이들 원소들을 다시 비활성 C_{18}$ 역상분리컬럼에서 pH3.0의 0.17M ${\alpha}$-HIBA/0.0038 M 1-pentanesulfonate 용리액으로 각각 분리하였다. 분리된 이들 원소들은 Arsenazo III를 사용하는 postcolumn반응으로 검출되었으며, 검출한계는 두 원서 모두 1ppb이었다.