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초록보기

The CRUD on the fuel cladding under the pressurized water reactor (PWR) operating condition causes several issues. The CRUD can act as thermal resistance and increases the local cladding temperature which accelerate the corrosion process. The hideout of boron inside the CRUD results in axial offset anomaly and reduces the plant's shutdown margin. Recently, there are efforts to revise the acceptance criteria of emergency core cooling systems (ECCS), and additionally require the modeling of the thermal resistance effect of the CRUD during the performance analysis. There is an urgent need for the evaluation of the effect of the CRUD deposition on the cladding heat transfer under PWR operating conditions, but the experimental database is very limited. The experimental facility called DISNY was designed and constructed to analyze the CRUD-related multi-physical phenomena, and the performance analysis of the constructed DISNY facility was conducted. The thermal-hydraulic and water chemistry conditions to simulate the CRUD growth under PWR operating conditions were established. The design characteristics and feasibility of the DISNY facility were validated by the MARS-KS code analysis and separate performance tests. In the current study, detailed design features, design validation results, and future utilization plans of the proposed DISNY facility are presented.

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권호기사 목록 테이블로 기사명, 저자명, 페이지, 원문, 기사목차 순으로 되어있습니다.
기사명 저자명 페이지 원문 목차
Structural and component characterization of the B4C neutron conversion layer deposited by magnetron sputtering Jingtao Zhu, Yang Liu, Jianrong Zhou, Zehua Yang, Hangyu Zhu, Xiaojuan Zhou, Jinhao Tan, Mingqi Cui, Zhijia Sun p. 3121-3125

Research of aluminum nitride water load for the 4.6 GHz 500 kW LHCD system of the CFETR Dingzhen Li, Liyuan Zhang, Lianmin Zhao, Fukun Liu, Min Cheng, Huaichuan Hu, Taian Zhou p. 3126-3132

Simulation of a neutron imaging detector prototype based on SiPM array readout Mengjiao Tang, Lianjun Zhang, Bin Tang, Gaokui He, Chang Huang, Jiangbin Zhao, Yang Liu p. 3133-3139

Tackling range uncertainty in proton therapy : development and evaluation of a new multi-slit prompt-gamma camera (MSPGC) system Youngmo Ku, Sehoon Choi, Jaeho Cho, Sehyun Jang, Jong Hwi Jeong, Sung Hun Kim, Sungkoo Cho, Chan Hyeong Kim p. 3140-3149

(An) intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-Ⅲ algorithm and an adaptive BP neural network Wen Zhou, Guomin Sun, Shuichiro Miwa, Zihui Yang, Zhuang Li, Di Zhang, Jianye Wang p. 3150-3163

(The) DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition : design, construction, and operation Ji Yong Kim, Yunju Lee, Ji Hyun Kim, In Cheol Bang p. 3164-3182

Radiochemical behavior of nitrogen species in high temperature water Young-Jin Kim, Geun Dong Song, Seung Heon Baek, Beom Kyu Kim, Jin Sik Cheon, Jun Hwan Kim, Hee-Sang Shim, Soon-Hyeok Jeon, Hyunmyung Kim p. 3183-3193

Development and validation of diffusion based CFD model for modelling of hydrogen and carbon monoxide recombination in passive autocatalytic recombiner Bhuvaneshwar Gera, Vishnu Verma, Jayanta Chattopadhyay p. 3194-3201

Determination of k0 factors of short-lived nuclides 46mSc and 110Ag for the k0-NAA Truong Son Truong, Van Doanh Ho, Manh Dung Ho p. 3202-3205

Feasibility study on fiber-optic inorganic scintillator array sensor system for multi-dimensional scanning of radioactive waste Jae Hyung Park, Siwon Song, Seunghyeon Kim, Jinhong Kim, Seunghyun Cho, Cheol Ho Pyeon, Bongsoo Lee p. 3206-3212

Verification of neutronics and thermal-hydraulic coupled system with pin-by-pin calculation for PWR core Zhigang Li, Junjie Pan, Bangyang Xia, Shenglong Qiang, Wei Lu, Qing Li p. 3213-3228

Estimation of yield strength due to neutron irradiation in a pressure vessel of WWER-1000 reactor based on the correction of the secondary displacement model Elaheh Moslemi-Mehni, Farrokh Khoshahval, Reza Pour-Imani, M.A. Amirkhani-Dehkordi p. 3229-3240

Analyses on the recriticality and sub-critical boron concentrations during late phase of a severe accident of pressurized water reactors Yoonhee Lee, Yong Jin Cho, Kukhee Lim p. 3241-3251

Study on the influence of hold-down spring on the vibration characteristics of core barrel Tiancai Tan, Lei Sun, Litao Liu, Jie Yang p. 3252-3259

Thickness measurements of a Cr coating deposited on Zr-Nb alloy plates using an ECT pancake sensor Jeong Won Park, Bonggyu Ji, Daegyun Ko, Hun Jang, Wonjae Choi p. 3260-3267

(The) radiation shielding proficiency and hyperspectral-based spatial distribution of lateritic terrain mapping in irikkur block, Kannur, Kerala S. Arivazhagan, K.A. Naseer, K.A. Mahmoud, N.K. Libeesh, K.V. Arun Kumar, K.ChV. Naga Kumar, M.I. Sayyed, Mohammed S. Alqahtani, E. El Shiekh, Mayeen Uddin Khandaker p. 3268-3276

Deep reinforcement learning for a multi-objective operation in a nuclear power plant Junyong Bae, Jae Min Kim, Seung Jun Lee p. 3277-3290

Molybdenum isotopes separation using squared-off optimized cascades Mahdi Aghaie, Valiyollah Ghazanfari p. 3291-3300

High fidelity transient solver in STREAM based on multigroup coarse-mesh finite difference method Anisur Rahman, Hyun Chul Lee, Deokjung Lee p. 3301-3312

Experimental investigation on critical heat flux in bilaterally heated annulus with equal heat flux on both sides Miao Gui, Junliang Guo, Huanjun Kong, Pan Wu, Jianqiang Shan, Yujiao Peng p. 3313-3319

Thermal-hydraulic behavior simulations of the reactor cavity cooling system (RCCS) experimental facility using Flownex Marcos S. Sena, Yassin A. Hassan p. 3320-3325

Dynamics of the IBR-2M reactor at a power pulse repetition frequency of 10 Hz Yu.N. Pepelyshev, D. Sumkhuu p. 3326-3333

Study on changes in electrical and switching characteristics of NPT-IGBT devices by fast neutron irradiation Hani Baek, Byung Gun Park, Chaeho Shin, Gwang Min Sun p. 3334-3341

Evaluation of the seismic performance of butt-fusion joint in large diameter polyethylene pipelines by full-scale shaking table test Jianfeng Shi, Ying Feng, Yangji Tao, Weican Guo, Riwu Yao, Jinyang Zheng p. 3342-3351

Study on (n, α) reactions for the production of 51Cr, 89Sr, 99Tc, 131I, 133Xe, 137Cs and 153Sm radioisotopes used in nuclear medicine Hallo M. Abdullah, Ali H. Ahmed p. 3352-3358

Discrimination of neutrons and gamma-rays in plastic scintillator based on spiking cortical model Bing-Qi Liu, Hao-Ran Liu, Lan Chang, Yu-Xin Cheng, Zhuo Zuo, Peng Li p. 3359-3366

Numerical investigation of turbulent lid-driven flow using weakly compressible smoothed particle hydrodynamics CFD code with standard and dynamic LES models Tae Soo Choi, Eung Soo Kim p. 3367-3382

Novel polyvinyl alcohol film dosimeter containing 3-(4,5-dimethylthiazol-2-yl)-2,5-diphenyltetrazolium bromide dye for high dose application Khalid A. Rabaeh, Ahmed A. Basfar, Issra' M.E. Hammoudeh p. 3383-3387

Modeling and simulation of VERA core physics benchmark using openmc code Abdullah O. Albugami, Abdullah S. Alomari, Abdullah I. Almarshad p. 3388-3400

Monte carlo simulations for gamma-ray spectroscopy using bismuth nanoparticle-containing plastic scintillators with spectral subtraction Taeseob Lim, Siwon Song, Seunghyeon Kim, Jae Hyung Park, Jinhong Kim, Cheol Ho Pyeon, Bongsoo Lee p. 3401-3408

Physics informed neural networks for surrogate modeling of accidental scenarios in nuclear power plants Federico Antonello, Jacopo Buongiorno, Enrico Zio p. 3409-3416

Real-time monitoring of ultra-high dose rate electron beams using bremsstrahlung photons Hyun Kim, Dong Hyeok Jeong, Sang Koo Kang, Manwoo Lee, Heuijin Lim, Sang Jin Lee, Kyoung Won Jang p. 3417-3422

Using machine learning to forecast and assess the uncertainty in the response of a typical PWR undergoing a steam generator tube rupture accident Tran Canh Hai Nguyen, Aya Diab p. 3423-3440

Determination of X-ray and gamma-ray shielding capabilities of recycled glass derived from deteriorated silica gel P. Sopapan, O. Jaiboon, R. Laopaiboon, C. Yenchai, C. Sriwunkum, S. Issarapanacheewin, T. Akharawutchayanon, K. Yubonmhat p. 3441-3449

Homogenized cross-section generation for pebble-bed type high-temperature gas-cooled reactor using NECP-MCX Shuai Qin, Yunzhao Li, Qingming He, Liangzhi Cao, Yongping Wang, Yuxuan Wu, Hongchun Wu p. 3450-3463

Geometry optimization of dispersed U-Mo fuel for light water reactors Ondrej Novak, Pavel Suk, Dusan Kobylka, Martin Sevecek p. 3464-3471

Seismic evaluation of different types of electrical cabinets in nuclear power plants considering coupling effects : experimental and numerical study Md Kamrul Hasan Ikbal, Dong Van Nguyen, Seokchul Kim, Dookie Kim p. 3472-3484

Determining plasma boundary in Alvand-U tokamak Yahya Sadeghi p. 3485-3492

Reevaluation of failure criteria location and novel improvement of 1/4 PCCV high fidelity simulation model under material uncertainty quantifications Bu-Seog Ju, Ho-Young Son p. 3493-3505

Evaluation of neutron attenuation properties using helium-4 scintillation detector for dry cask inspection Jihun Moon, Jisu Kim, Heejun Chung, Sung-Woo Kwak, Kyung Taek Lim p. 3506-3513

참고문헌 (51건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 J.W. Yeon, I.K. Choi, K.K. Park, H.M. Kwon, K. Song, Chemical analysis of fuel crud obtained from Korean nuclear power plants, J. Nucl. Mater. 404 (2010)160-164, https://doi.org/10.1016/j.jnucmat.2010.07.024. 미소장
2 J. Deshon, Evaluation of Fuel Cladding Corrosion and Corrosion Product Deposits from Callaway Cycle, 14, 2006. Palo Alto, CA, www.epri.com. 미소장
3 G. Wang, A. Byers, M. Young, Simulated Fuel Crud Thermal Conductivity Measurements under Pressurized Water Reactor Conditions, 2011. Palo Alto, CA, www.epri.com. 미소장
4 J. Deshon, D. Hussey, B. Kendrick, J. Mcgurk, J. Secker, M. Short, Pressurized water reactor fuel crud and corrosion modeling, JOM 63 (2011) 64-72. www. tms.org/jom.html. 미소장
5 M.P. Short, D. Hussey, B.K. Kendrick, T.M. Besmann, C.R. Stanek, S. Yip, Multiphysics modeling of porous CRUD deposits in nuclear reactors, J. Nucl. Mater. 443 (2013) 579-587, https://doi.org/10.1016/j.jnucmat.2013.08.014. 미소장
6 P. Cohen, Heat and mass transfer for boiling in porous deposits with chimenys, AlChe Symphsium Series 70 (1972) 71-80. 미소장
7 C. Pan, B.G. Jones, A.J. Machiels, Concentration levels of solutes in porous deposits with chimneys under WICK boiling conditions, Nucl. Eng. Des. 99(1987) 317-327. 미소장
8 D.Y. Yeo, H.C. No, Modeling heat transfer through chimney-structured porous deposit formed in pressurized water reactors, Int. J. Heat Mass Tran. 108 (2017)868-879, https://doi.org/10.1016/J.IJHEATMASSTRANSFER.2016.12.046. 미소장
9 J. Henshaw, J.C. McGurk, H.E. Sims, A. Tuson, S. Dickinson, J. Deshon, A model of chemistry and thermal hydraulics in PWR fuel crud deposits, J. Nucl. Mater. 353 (2006) 1-11, https://doi.org/10.1016/J.JNUCMAT.2005.01.028. 미소장
10 I.U. Haq, N. Cinosi, M. Bluck, G. Hewitt, S. Walker, Modelling heat transfer and dissolved species concentrations within PWR crud, Nucl. Eng. Des. 241 (2011)155-162, https://doi.org/10.1016/J.NUCENGDES.2010.10.018. 미소장
11 N. Cinosi, I. Haq, M. Bluck, S.P. Walker, The effective thermal conductivity of crud and heat transfer from crud-coated PWR fuel, Nucl. Eng. Des. 241 (2011)792-798, https://doi.org/10.1016/J.NUCENGDES.2010.12.015. 미소장
12 S. Seo, B. Park, S.J. Kim, H.C. Shin, S.J. Lee, M. Lee, S. Choi, BOTANI: high-fidelity multiphysics model for boron chemistry in CRUD deposits, Nucl. Eng. Technol. 53 (2021) 1676-1685, https://doi.org/10.1016/J.NET.2020.11.008. 미소장
13 D.Y. Yeo, H.C. No, Modeling film boiling within chimney-structured porous media and heat pipes, Int. J. Heat Mass Tran. 124 (2018) 576-585, https://doi.org/10.1016/J.IJHEATMASSTRANSFER.2018.03.093. 미소장
14 M. Jin, M. Short, Multiphysics modeling of two-phase film boiling within porous corrosion deposits, J. Comput. Phys. 316 (2016) 504-518, https://doi.org/10.1016/J.JCP.2016.03.013. 미소장
15 P. Saha, N. Aksan, J. Andersen, J. Yan, J.P. Simoneau, L. Leung, F. Bertrand, K. Aoto, H. Kamide, Issues and future direction of thermal-hydraulics research and development in nuclear power reactors, Nucl. Eng. Des. 264 (2013) 3-23, https://doi.org/10.1016/j.nucengdes.2012.07.023. 미소장
16 J. Deshon, PWR Axial Offset Anomaly (AOA) Guidelines, Revision 1, Palo Alto, CA, 2004. 미소장
17 R. Hu, M.S. Kazimi, M.E. Leyse, CONSIDERING THE THERMAL RESISTANCE OF CRUD IN LOCA ANALYSIS, 101, Transaction of the American Nuclear Society, 2009, pp. 590-592. 미소장
18 J. Lee, H. Jeong, Y. Bang, Thermal resistance effects of crud and oxide layers to the safety analysis, in: 2018 TOPFUEL, Prague, Czech Republic, 2018. 미소장
19 I. Dumnernchanvanit, N.Q. Zhang, S. Robertson, A. Delmore, M.B. Carlson, D. Hussey, M.P. Short, Initial experimental evaluation of crud-resistant materials for light water reactors, J. Nucl. Mater. 498 (2018) 1-8, https://doi.org/10.1016/J.JNUCMAT.2017.10.010. 미소장
20 S.H. Baek, H.S. Shim, J.G. Kim, D.H. Hur, Effect of chemical etching of fuel cladding surface on crud deposition behavior in simulated primary water of PWRs at 328  °C, Ann. Nucl. Energy 116 (2018) 69-77, https://doi.org/10.1016/J.ANUCENE.2018.02.030. 미소장
21 S.H. Baek, H.S. Shim, J.G. Kim, D.H. Hur, Effects of heat flux on fuel crud deposition and sub-cooled nucleate boiling in simulated PWR primary water at 13 MPa, Ann. Nucl. Energy 133 (2019) 178-185, https://doi.org/10.1016/J.ANUCENE.2019.05.022. 미소장
22 W.A. Byers, G. Wang, M.Y. Young, J. Deshon, Simulation of PWR crud, in:ICONE22, Prague, Czech Republic, 2014. 미소장
23 G. Wang, W.A. Byers, M.Y. Young, J. Deshon, Z. Karoutas, R.L. Oelrich, Thermal conductivity measurement for simulated PWR crud, in: ICONE21, Chengdu, China, 2013. 미소장
24 Z. Karoutas, G. Wang, W.A. Byers, Critical heat flux and crud WALT loop measurements for westinghouse accident tolerant fuel, in: 2019 TOPFUEL, Seattle, WA, 2019. 미소장
25 R. v Macbeth, R. Trenberth, R.W. Wood, An Investigation into the Effect of “CRUD” Deposits on Surface Temperature, Dry-Out and Pressure Drop, with Forced Convection Boiling of Water at 69 Bar in an Annular Test Section, UKAEA Reactor Group, 1971. 미소장
26 J. Buongiorno, Can corrosion and CRUD actually improve safety margins in LWRs? Ann. Nucl. Energy 63 (2014) 9-21, https://doi.org/10.1016/j.anucene.2013.07.019. 미소장
27 J.Y. Kim, H.J. Kim, I.C. Bang, Design study of CRUD thermal properties characterization facility DISNY under pressurized water reactor normal operating condition, in: Advances in Thermal Hydraulics, ATH 2022), Anaheim, CA, USA, 2022, pp. 563-574, https://doi.org/10.13182/T126-38228. 미소장
28 J.Y. Kim, Y. Lee, J. Ham, J.H. Kim, I.C. Bang, Establishment of experimental facility to investigate the sub-cooled boiling heat transfer characteristics of fouled cladding surface at PWR conditions, The KSFM Journal of Fluid Machinery 25 (2022) 12-21, https://doi.org/10.5293/kfma.2022.25.5.012. 미소장
29 Khnp, Final Safety Analysis Report for Hanbit Unit 5, 6, 1997 (Chapter 4). 미소장
30 Khnp, Final Safety Analysis Report for Shin-Kori Unit 3, 4, 2008 (Chapter 4). 미소장
31 B.A. Khuwaileh, F.I. Al-Hamadi, D. Hartanto, Z. Said, M. Ali, On the performance of nanofluids in APR 1400 PLUS7 assembly: neutronics, Ann. Nucl. Energy 144 (2020), 107508, https://doi.org/10.1016/J.ANUCENE.2020.107508. 미소장
32 J.-J. Jeong, K.S. Ha, B.D. Chung, W.J. Lee, Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3. 1, Ann. Nucl. Energy 26 (1999)1611-1642. 미소장
33 J.A. Sawicki, Characterization of Corrosion Products on the Callaway Cycle 9PWR Core, 2001, https://doi.org/10.13140/2.1.3645.4087. Palo Alto, CA. 미소장
34 J. Ham, Y. Lee, S.C. Yoo, M.P. Short, C.B. Bahn, J.H. Kim, Effect of TiN coating on the fouling behavior of crud on pressurized water reactor fuel cladding, J. Nucl. Mater. 549 (2021), 152870, https://doi.org/10.1016/J.JNUCMAT.2021.152870. 미소장
35 Y. Lee, S.C. Yoo, D. Park, J. Ham, J.H. Kim, Chemistry change of CRUD with various metal ion concentration conditions in PWR fuel cladding, in: 20th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Springer, Snowmass Village, CO, USA, 2022. 미소장
36 Y. Lee, J. Ham, D.H. Park, S.C. Yoo, J.H. Kim, Microstructure change of crud with various heat flux conditions, in: PWR FUEL CLADDING, 2021TOPFUEL, Santander, Spain, 2021. 미소장
37 H.W. Coleman, W.G. Steele, Experimentation, Validation, and Uncertainty Analysis for Engineers, John Wiley & Sons, 2018. 미소장
38 M. Awais, A.A. Bhuiyan, Recent advancements in impedance of fouling resistance and particulate depositions in heat exchangers, Int. J. Heat Mass Tran. 141(2019) 580-603, https://doi.org/10.1016/J.IJHEATMASSTRANSFER.2019.07.011. 미소장
39 A. Fguiri, C. Marvillet, M.R. Jeday, Estimation of fouling resistance in a phosphoric acid/steam heat exchanger using inverse method, Appl. Therm. Eng. 192(2021), 116935, https://doi.org/10.1016/J.APPLTHERMALENG.2021.116935. 미소장
40 T.L. Bergman, T.L. Bergman, F.P. Incropera, D.P. Dewitt, A.S. Lavine, Fundamentals of Heat and Mass Transfer, John Wiley & Sons, 2011. 미소장
41 G. Wang, Improved CRUD Heat Transfer Model for Dryout on Fuel Pin Surfaces at PWR Operating Conditions, Doctoral thesis, Pennsylvania State University, 2009. 미소장
42 J.B. Lee, Description Report of ATLAS Facility and Instrumentation (Third Revision), Deajeon, Korea, 2020. 미소장
43 J.H. Lienhard, On the commonality of equations for natural convection from immersed bodies, Int. J. Heat Mass Tran. 16 (1973) 2121-2123, https://doi.org/10.1016/0017-9310(73)90116-6. 미소장
44 F.W. Dittus, L.M.K. Boelter, Heat Transfer in Automobile Radiators of Tubular Type, 443-461, 2, Berkeley Univ. California. Publ. Eng., 1930, p. 13. 미소장
45 W.H. Jens, P.A. Lottes, Analysis of Heat Transfer, Burnout, Pressure Drop and Density Date for High-Pressure Water, Argonne National Lab., 1951. 미소장
46 J.R.S. Thom, W.M. Walker, T.A. Fallon, G.F.S. Reising, Boiling in Subcooled Water during Flow up Heated Tubes or Annuli, Paper Presented at the Symposium on Boiling Heat Transfer in Steam Generating Units and Heat Exchangers, Manchester, England. September 15-16, 1965. Cited in JG Collier, Convective Boiling , Cited in JG Collier, Convective Boiling and Condensation. (1972). 미소장
47 J.C. Chen, Correlation for boiling heat transfer to saturated fluids in convective flow, Ind. Eng. Chem. Process Des. Dev. 5 (1966) 322-329. 미소장
48 H.K. Forster, N. Zuber, Dynamics of vapor bubbles and boiling heat transfer, AIChE J. 1 (1955) 531-535. 미소장
49 Youngjae Park, Experimental Study about the Effects of CRUD on Quenching Heat Transfer of Simulated Fuel Rod in Single Flow Channel under PWR Reflood Flow Conditions, Doctoral thesis, Kyunghee University, 2021. 미소장
50 C. Sauder, Ceramic Matrix Composites: Nuclear Applications, Ceramic Matrix Composites: Materials, Modeling and Technology, 2014, pp. 609-646. 미소장
51 D. Lee, B. Elward, P. Brooks, R. Umretiya, J. Rojas, M. Bucci, R.B. Rebak, M. Anderson, Enhanced flow boiling heat transfer on chromium coated zircaloy-4 using cold spray technique for accident tolerant fuel (ATF) materials, Appl. Therm. Eng. 185 (2021), 116347, https://doi.org/10.1016/J.APPLTHERMALENG.2020.116347. 미소장

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