• 제목/요약/키워드: Static salt reactor

검색결과 5건 처리시간 0.022초

Core design study of the Wielenga Innovation Static Salt Reactor (WISSR)

  • T. Wielenga;W.S. Yang;I. Khaleb
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.922-932
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    • 2024
  • This paper presents the design features and preliminary design analysis results of the Wielenga Innovation Static Salt Reactor (WISSR). The WISSR incorporates features that make it both flexible and inherently safe. It is based on innovative technology that controls a nuclear reactor by moving molten salt fuel into or out of the core. The reactor is a low-pressure, fast spectrum transuranic (TRU) burner reactor. Inherent shutdown is achieved by a large negative reactivity feedback of the liquid fuel and by the expansion of fuel out of the core. The core is made of concentric, thin annular fuel chambers containing molten fuel salt. A molten salt coolant passes between the concentric fuel chambers to cool the core. The core has both fixed and variable volume fuel chambers. Pressure, applied by helium gas to fuel reservoirs below the core, pushes fuel out of a reservoir and up into a set of variable volume chambers. A control system monitors the density and temperature of the fuel throughout the core. Using NaCl-(TRU,U)Cl3 fuel and NaCl-KCl-MgCl2 coolant, a road-transportable compact WISSR core design was developed at a power level of 1250 MWt. Preliminary neutronics and thermal-hydraulics analyses demonstrate the technical feasibility of WISSR.

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

  • Ezell, N. Dianne Bull;Raiman, Stephen S.;Kurley, J. Matt;McDuffee, Joel
    • Nuclear Engineering and Technology
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    • 제53권3호
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    • pp.920-926
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    • 2021
  • Capsules containing NaCl-MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation-corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts.

Effect of process parameters on the recovery of thorium tetrafluoride prepared by hydrofluorination of thorium oxide, and their optimization

  • Kumar, Raj;Gupta, Sonal;Wajhal, Sourabh;Satpati, S.K.;Sahu, M.L.
    • 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.

${250MW_th}$ AMBIDEXTER 원자로의 정특성 최적설계 (Some Static Design Characteristics of the Optimized ${250MW_th}$ AMBIDEXTER Core)

  • 조재국;원성희;임현진;김태규;윤정선;오세기
    • 한국에너지공학회:학술대회논문집
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    • 한국에너지공학회 1999년도 춘계 학술발표회 논문집
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    • pp.113-118
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    • 1999
  • AMBIDEXTER(Advanced Molten-salt Break-even Inherently-safe Dual-mission Experimental and TEst Reactor)는 고온저압의 Th/$^{233}$ U 불화용융염을 핵연료로 사용하므로 피복관이나 독립된 냉각재 없이 핵연료 자체가 열수송 매체로서 순환하는 원자로시스템개념으로서 저농축 $^{235}$ U 고체 핵연료를 사용하는 기존의 원자력 발전시스템이 안고있는 핵확산과 안전성 등의 고유문제를 해결할 수 있는 혁신형 차세대 원자력 발전시스템이다.(중략)

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밀폐형 ATAD system을 이용한 하수슬러지/음식물쓰레기 통합처리 공정 설계 (Design of waste Sludge/Food Waste Biological Treatment Process using Closed ATAD System)

  • 권혁영;지영환;송한조;김성중
    • 유기물자원화
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    • 제8권4호
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    • pp.129-137
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    • 2000
  • 본 연구에서는 도시고함수율 유기성폐기물(MWWT)의 처리를 위하여, 음식물 쓰레기의 처리에 사용되었던 컨테이너 호기성 퇴비화 시스템과, 계분 및 축분처리에 사용되었던 직립 상향 기계식 교반기를 조합하여 개발하였다. 호기성 처리 공정은 운전이 쉽다는 점과 운전비용이 저렴하다는 점, 자연에서 이용하기 가장 편리한 안정된 부산물을 만들 수 있다는 장점에도 불구하고, 염분의 농축, 과도한 부형제의 사용에 의한 경제적 부담의 증가 및 설비의 대형화 등의 장애물을 가지고 있다. 개발된 공정은 이러한 문제점을 보완하고자 하수슬러지는 초기의 수분조절 및 고속발효를 위해 직립 밀폐형 반응조에서 5일간, 음식물쓰레기는 탈염과 수분조절을 위해 밀폐형 무교반 필터에서, 침출수는 폐수처리 장치에서 처리하였다. 실험결과 국내 퇴비에 품질규격을 만족하면서 부자재의 사용량을 3% 이내로 조절할 수 있어 기존공정의 문제점을 해결할 수 있는 가능성을 확인하였다.

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