• 제목/요약/키워드: VHTR

검색결과 106건 처리시간 0.018초

소형 공정열교환기 시제품 고온구조해석 - 용접부 물성치를 고려한 해석 - (High-Temperature Structural Analysis of a Small-Scale PHE Prototype - Analysis Considering Material Properties in Weld Zone -)

  • 송기남;홍성덕;박홍윤
    • 대한기계학회논문집A
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    • 제36권10호
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    • pp.1289-1295
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    • 2012
  • 수소를 대량으로 생산하기 위한 원자력수소생산시스템에서 공정열교환기는 초고온가스로로부터 생성된 초고온 열을 화학반응공정으로 전달하는 핵심기기이다. 한국원자력연구원에 구축되어 있는 소형가스루프에서 Hastelloy-X 로 제작된 소형 공정열교환기(PHE) 시제품에 대한 성능시험이 수행되고 있다. 그동안 소형 PHE 시제품에 대한 고온구조해석은 용접부의 기계적 물성변화를 고려하지 않은 해석이 주로 수행되었다. 본 연구에서는 계장화 압입시험으로부터 얻은 용접부 기계적 물성치를 이용하여 고온구조해석을 수행하고 그 결과를 분석하였다.

Corrosion of Selected Materials in Boiling Sulfuric Acid for the Nuclear Power Industries

  • Kim, Dong-Jin;Lee, Han Hee;Kwon, Hyuk Chul;Kim, Hong Pyo;Hwang, Seong Sik
    • Corrosion Science and Technology
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    • 제6권2호
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    • pp.37-43
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    • 2007
  • Iodine sulfur (IS) process is one of the promising processes for a hydrogen production by using a high temperature heat generated by a very high temperature gas cooled reactor(VHTR) in the nuclear power industries. Even though the IS process is very efficient for a hydrogen production and it is not accompanied by a carbon dioxide evolution, the highly corrosive environment of the process limits its application in the industry. Corrosion tests of selected materials were performed in sulfuric acid to select appropriate materials compatible with the IS process. The materials used in this work were Fe-Cr alloys, Fe-Ni-Cr alloys, Fe-Si alloys, Ni base alloys, Ta, Ti, Zr, SiC, Fe-Si, etc. The test environments were 50 wt% sulfuric acid at $120^{\circ}C$ and 98 wt% at $320^{\circ}C$. Corrosion rates were measured by using a weight change after an immersion. The surface morphologies and cross sectional areas of the corroded materials were examined by using SEM equipped with EDS. Corrosion behaviors of the materials were discussed in terms of the chemical composition of the materials, a weight loss, the corrosion morphology, the precipitates in the microstructure and the surface layer composition.

용접 물성치를 고려한 공정열교환기 시제품의 거시적 고온구조해석 (Macroscopic High-Temperature Structural Analysis of PHE Prototypes Considering Weld Material Properties)

  • 송기남;홍성덕;박홍윤
    • 대한기계학회논문집A
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    • 제36권9호
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    • pp.1095-1101
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    • 2012
  • 수소를 대량으로 생산하기 위한 원자력수소생산시스템에서 공정열교환기(PHE)는 초고온가스로로 부터 생성된 초고온 열을 화학반응공정으로 전달하는 핵심기기이다. 한국원자력연구원에 구축되어 있는 소형 질소가스루프에서 Hastelloy-X로 제작된 소형 및 중형 PHE 시제품들에 대한 성능시험이 수행되고 있다. 그동안 PHE 시제품에 대한 거시적 고온구조해석은 용접 물성치의 부재로 인해 모재의 물성치만을 사용한 해석이 주로 수행되었으나 본 연구에서는 계장형 압입시험법으로부터 얻은 용접부 기계적 물성치를 이용하여 거시적 고온구조해석을 수행하고 그 결과를 비교, 분석하였다.

고점성 모사용액 내 Carbon Black 입자의 분산특성 (Dispersion Characteristics of Carbon Black Particles in a High Viscous Simulated Solution)

  • 정경채;엄성호;김연구;조문성
    • 공업화학
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    • 제24권2호
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    • pp.165-170
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    • 2013
  • 초고온가스로 핵연료 구형 UCO (uranium oxycarbide) 입자 제조과정 중 중간화합물 제조에서 적용하고 있는 내부겔화공정을 대체하기 위해 외부겔화공정을 도입하는 연구가 진행 중에 있다. 외부겔화공정을 이용해서 구형 UCO입자를 제조하기 위한 사전실험으로, 중간화합물인 ADU (ammonium di-uranate) 겔 입자를 제조하기 위한 원료용액인 모사 broth 용액을 제조하여 카본블랙 입자를 분산시키는 실험이 수행되었다. 다양한 종류의 카본블랙 입자를 사용해서 모사 broth 용액에 분산실험을 수행한 결과, Cabot G 제품이 용액상에서 분산안정성과 균일한 분산상태를 나타내고 있어서, 본 연구의 카본블랙으로 선정되었다. 또한 나노크기 입자로 응집된 카본블랙 입자를 고점성 액상물질에 효율적으로 분산시키기 위해서는, 금속염용액에 카본블랙 입자를 투입하고 ultrasonic force를 이용해서 응집입자를 해체한 다음, 고점성 물질인 PVA (poly vinyl alcohol)를 투입하여 강력한 기계식혼합기를 이용해서 6000 rpm으로 2차 분산 혼합시키는 경우, ultrasonic force에 의한 broth 용액의 물성이 유지되면서 카본블랙 입자의 분산안정성과 분산상태가 양호한 broth용액을 얻을 수 있었다.

POTENTIAL APPLICATIONS FOR NUCLEAR ENERGY BESIDES ELECTRICITY GENERATION: A GLOBAL PERSPECTIVE

  • Gauthier, Jean-Claude;Ballot, Bernard;Lebrun, Jean-Philippe;Lecomte, Michel;Hittner, Dominique;Carre, Frank
    • Nuclear Engineering and Technology
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    • 제39권1호
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    • pp.31-42
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    • 2007
  • Energy supply is increasingly showing up as a major issue for electricity supply, transportation, settlement, and process heat industrial supply including hydrogen production. Nuclear power is part of the solution. For electricity supply, as exemplified in Finland and France, the EPR brings an immediate answer; HTR could bring another solution in some specific cases. For other supply, mostly heat, the HTR brings a solution inaccessible to conventional nuclear power plants for very high or even high temperature. As fossil fuels costs increase and efforts to avoid generation of Greenhouse gases are implemented, a market for nuclear generated process heat will be developed. Following active developments in the 80's, HTR have been put on the back burner up to 5 years ago. Light water reactors are widely dominating the nuclear production field today. However, interest in the HTR technology was renewed in the past few years. Several commercial projects are actively promoted, most of them aiming at electricity production. ANTARES is today AREVA's response to the cogeneration market. It distinguishes itself from other concepts with its indirect cycle design powering a combined cycle power plant. Several reasons support this design choice, one of the most important of which is the design flexibility to adapt readily to combined heat and power applications. From the start, AREVA made the choice of such flexibility with the belief that the HTR market is not so much in competition with LWR in the sole electricity market but in the specific added value market of cogeneration and process heat. In view of the volatility of the costs of fossil fuels, AREVA's choice brings to the large industrial heat applications the fuel cost predictability of nuclear fuel with the efficiency of a high temperature heat source tree of Greenhouse gases emissions. The ANTARES module produces 600 MWth which can be split into the required process heat, the remaining power drives an adapted prorated electric plant. Depending on the process heat temperature and power needs, up to 80% of the nuclear heat is converted into useful power. An important feature of the design is the standardization of the heat source, as independent as possible of the process heat application. This should expedite licensing. The essential conditions for success include: ${\bullet}$ Timely adapted licensing process and regulations, codes and standards for such application and design ${\bullet}$ An industry oriented R&D program to meet the technological challenges making the best use of the international collaboration. Gen IV could be the vector ${\bullet}$ Identification of an end user(or a consortium of) willing to fund a FOAK

Investigation of thermal hydraulic behavior of the High Temperature Test Facility's lower plenum via large eddy simulation

  • Hyeongi Moon ;Sujong Yoon;Mauricio Tano-Retamale ;Aaron Epiney ;Minseop Song;Jae-Ho Jeong
    • Nuclear Engineering and Technology
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    • 제55권10호
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    • pp.3874-3897
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    • 2023
  • A high-fidelity computational fluid dynamics (CFD) analysis was performed using the Large Eddy Simulation (LES) model for the lower plenum of the High-Temperature Test Facility (HTTF), a ¼ scale test facility of the modular high temperature gas-cooled reactor (MHTGR) managed by Oregon State University. In most next-generation nuclear reactors, thermal stress due to thermal striping is one of the risks to be curiously considered. This is also true for HTGRs, especially since the exhaust helium gas temperature is high. In order to evaluate these risks and performance, organizations in the United States led by the OECD NEA are conducting a thermal hydraulic code benchmark for HTGR, and the test facility used for this benchmark is HTTF. HTTF can perform experiments in both normal and accident situations and provide high-quality experimental data. However, it is difficult to provide sufficient data for benchmarking through experiments, and there is a problem with the reliability of CFD analysis results based on Reynolds-averaged Navier-Stokes to analyze thermal hydraulic behavior without verification. To solve this problem, high-fidelity 3-D CFD analysis was performed using the LES model for HTTF. It was also verified that the LES model can properly simulate this jet mixing phenomenon via a unit cell test that provides experimental information. As a result of CFD analysis, the lower the dependency of the sub-grid scale model, the closer to the actual analysis result. In the case of unit cell test CFD analysis and HTTF CFD analysis, the volume-averaged sub-grid scale model dependency was calculated to be 13.0% and 9.16%, respectively. As a result of HTTF analysis, quantitative data of the fluid inside the HTTF lower plenum was provided in this paper. As a result of qualitative analysis, the temperature was highest at the center of the lower plenum, while the temperature fluctuation was highest near the edge of the lower plenum wall. The power spectral density of temperature was analyzed via fast Fourier transform (FFT) for specific points on the center and side of the lower plenum. FFT results did not reveal specific frequency-dominant temperature fluctuations in the center part. It was confirmed that the temperature power spectral density (PSD) at the top increased from the center to the wake. The vortex was visualized using the well-known scalar Q-criterion, and as a result, the closer to the outlet duct, the greater the influence of the mainstream, so that the inflow jet vortex was dissipated and mixed at the top of the lower plenum. Additionally, FFT analysis was performed on the support structure near the corner of the lower plenum with large temperature fluctuations, and as a result, it was confirmed that the temperature fluctuation of the flow did not have a significant effect near the corner wall. In addition, the vortices generated from the lower plenum to the outlet duct were identified in this paper. It is considered that the quantitative and qualitative results presented in this paper will serve as reference data for the benchmark.