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In various small modular reactor (SMR) designs currently under development, the conventional concrete containment building has been replaced by a metal containment vessel (MCV). In these systems, the gap between the MCV and the reactor pressure vessel is filled with gas or vacuumed weakly, effectively suppressing conduction and convection heat transfer. However, thermal radiation remains the major mode of heat transfer during normal operation. The objective of this study was to investigate the heat-transfer mechanisms in integral pressurized water reactor (IPWR)-type SMRs under various gas-filled conditions using computational fluid dynamics. The use of thermal radiation shielding (TRS) with a much lower emissivity material than the MCV surface was also evaluated. The results showed that thermal radiation was always the dominant contributor to heat loss (48–97%), while the conjugated effects of the gas candidates on natural convection and thermal radiation varied depending on their thermal and radiative properties, including absorption coefficient. The TRS showed an excellent insulation performance, with a reduction in the total heat loss of 56–70% under the relatively low temperatures of the IPWR system, except for carbon dioxide (13%). Consequently, TRS can be utilized to enhance the thermal efficiency of SMR designs by suppressing the heat loss through the MCV.

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권호기사 목록 테이블로 기사명, 저자명, 페이지, 원문, 기사목차 순으로 되어있습니다.
기사명 저자명 페이지 원문 목차
Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility Omar S. Al-Yahia, Ivor Clifford, Hakim Ferroukhi p. 2893-2905

(An) estimation and radioactivity measurement for radiocarbon(14C) in the Korean nuclear power plants Seo Ra Yang, Jin Hong Lee, Jae Hwan Yang, Geun-Il Park p. 2906-2915

Radiation tolerant capacitor-SRAM without area overhead Eunju Jo, Hosang Yoon, Hongjoon Park, Woo-young Choi, Inyong Kwon p. 2916-2922

Invulnerability analysis of nuclear accidents emergency response organization network based on complex network Wen Chen, Shuliang Zou, Changjun Qiu, Jianyong Dai, Meirong Zhang p. 2923-2936

Evaluation of MUF uncertainty based on GUM method for benchmark bulk handling facility Hyun Cheol Lee, Jung Youn Choi, Hana Seo, Hyun Ju Kim, Yewon Kim, Haneol Lee p. 2937-2947

Application of data-driven model reduction techniques in reactor neutron field calculations Zhaocai Xiang, Qiafeng Chen, Pengcheng Zhao p. 2948-2957

Fault diagnosis of nuclear power plant sliding bearing-rotor systems using deep convolutional generative adversarial networks Qi Li, Weiwei Zhang, Feiyu Chen, Guobing Huang, Xiaojing Wang, Weimin Yuan, Xin Xiong p. 2958-2973

(A) comprehensive examination of the linear and numerical stability aspects of the bubble collision model in the TRACE-1D two-fluid model applied to vertical disperse flow in a PWR core channel under loss of coolant accident conditions Satya Prakash Saraswat, Yacine Addad p. 2974-2989

Computational study of the nitrogen-16 source term in the ITER vacuum vessel cooling circuit through the coupling of system-level analysis code and CFD M. De Pietri, C. Fiorina, Y. Le Tonqueze, R. Juarez p. 2990-2998

(A) methodology to quantify effects of constitutive equations on safety analysis using integral effect test data ChoHwan Oh, Jeong Ik Lee p. 2999-3029

Research on mechanism of gas leakage in microchannels of steel containment vessels for nuclear power plants Min He, Yueyao Chen, Zhen Wu, Gangling Hou, Jialong Wang, Zhuangfei Li, Yuzhu Wang, Hanze Li p. 3030-3042

Analysis of heat-loss mechanisms with various gases associated with the surface emissivity of a metal containment vessel in a water-cooled small modular reactor Geon Hyeong Lee, Jae Hyung Park, Beomjin Jeong, Sung Joong Kim p. 3043-3066

Local mechanical properties of corrosion layers formed on T91 and SS316L steels after exposure to static liquid LBE at 500 °C for 1000 h obtained by nano-indentation Zhikun Zhou, Juan Du, Chenwen Tian, Xuhao Peng, Yabo Wu, Xi Lv, Yixiong Zhang, Ziguang Chen p. 3067-3075

Characterization of small single photon avalanche diode fabricated using standard 180 nm CMOS process for digital SiPM Jinseok Oh, Hakcheon Jeong, Min Sun Lee, Inyong Kwon p. 3076-3083

Photoneutron yield for an electron beam on tantalum and erbium deuteride Andrew K. Gillespie, Cuikun Lin, R.V. Duncan p. 3084-3089

Experimental study of the influence of borehole parameters on prompt fission neutron uranium logging and its corrections Pengfei Zhou, Bin Tang p. 3090-3096

Realistic estimation framework of radioactive release distributions into the environment during nuclear power plant accidents Wasin Vechgama, Jaehyun Cho p. 3097-3111

Crevice chemistry and corrosion in high temperature water : a review Young-Jin Kim, Chi Bum Bahn, Seung Heon Baek, Wonjun Choi, Geun Dong Song p. 3112-3122

Discrimination of dicentric chromosome from radiation exposure patient data using a pretrained deep learning model Soon Woo Kwon, Won Il Jang, Mi-Sook Kim, Ki Moon Seong, Yang Hee Lee, Hyo Jin Yoon, Susan Yang, Younghyun Lee, Hyung Jin Shim p. 3123-3128

In-situ TEM investigation of zirconium alloy under Kr+ single-beam and Kr+-He+ dual-beam synergetic irradiation Zhen Wang, Qing-Xue Yan, Zhong-Qiang Fang, Chen-Yang Lu p. 3129-3138

(An) explicit approximation of the central angle for the curved interface in double-circle model for horizontal two-phase stratified flow Taehwan Ahn, Dongwon Jeong, Jin-Yeong Bak, Jae Jun Jeong, Byongjo Yun p. 3139-3143

Reactor core design with practical gadolinia burnable absorbers for soluble boron-free operation in the innovative SMR Jin Sun Kim, Tae Sik Jung, Jooil Yoon p. 3144-3154

Assessing the nuclear weapons proliferation risks in nuclear energy newcomer countries : the case of small modular reactors Philseo Kim, Sunil S. Chirayath p. 3155-3166

Development of an AI-based remaining trip time prediction system for nuclear power plants Sang Won Oh, Ji Hun Park, Hye Seon Jo, Man Gyun Na p. 3167-3179

Parametric study on stress distribution of thin disk specimen of rupture disk corrosion test influencing SCC initiation using finite element analysis Tae Young Kim, Sung Woo Kim, Dong Jim Kim, Sang Tae Kim p. 3180-3187

Localization of hotspots via a lightweight system combining Compton imaging with a 3D lidar camera Mattias Simons, David De Schepper, Eric Demeester, Wouter Schroeyers p. 3188-3198

Machine learning‐based evaluation technology of 3D spatial distribution of residual radioactivity in large‐scale radioactive structures UkJae Lee, Phillip Chang, Nam-Suk Jung, Jonghun Jang, Jimin Lee, Hee-Seock Lee p. 3199-3209

Pediatric phantom library constructed from ICRP mesh-type reference computational phantoms (MRCPs) Suhyeon Kim, Bangho Shin, Chansoo Choi, Hyeonil Kim, Sangseok Ha, Beom Sun Chung, Haegin Han, Sungho Moon, Gahee Son, Jaehyo Kim, Ji Won Choi, Chan Hyeong Kim, Yeon Soo Yeom p. 3210-3223

Analysis of values-beliefs-norms of decommissioned nuclear power plant reestablishment acceptance in developing countries : a perspective from the Philippines Leo Miguel V. Tolentino, Ardvin Kester S. Ong, Josephine D. German p. 3224-3235

Neutronics analysis of the ion cyclotron resonance heating antenna of the China fusion engineering test reactor Gaoxiang Wang, Chengming Qin, Shanliang Zheng, Yongsheng Wang, Kun Xu, Huiqiang Ma p. 3236-3241

Multiscale modeling of smectite illitization in bentonite buffer of engineered barrier system Xinwei Xiong, Jiahui You, Kyung Jae Lee, Jin-Seop Kim p. 3242-3254

Whole-core analysis of Watts bar benchmark with three-dimensional MOC code STREAM3D Murat Serdar Aygul, Wonkyeong Kim, Deokjung Lee p. 3255-3267

Simulation-guided design of a target-cooling system for cyclotron-based isotope production Sang Chul Mun, Gyeol Chan Kang, Choong Mo Kang, Jung Young Kim, Kyo Chul Lee, Seyoung Oh p. 3268-3275

Development of uncertainty quantification module for VVER analysis in STREAM/RAST-V two-step method Jaerim Jang, Yunki Jo, Deokjung Lee p. 3276-3285

Research on design requirements for passive residual heat removal system of lead cooled fast reactor via model-based system engineering Mao Tang, Junqian Yang, Pengcheng Zhao, Kai Wang p. 3286-3297

Asymmetric nexus between nuclear energy technology budgets and carbon emissions in European economies : evidence from quantile-on-quantile estimation Shuifa Shen, Muhammad Zahir Faridi, Raima Nazar, Sajid Ali p. 3298-3306

Study on the shielding performance of bismuth oxide as a spent fuel dry storage container based on Monte Carlo simulation Guo-Qiang Zeng, Shuang Qi, Peng Cheng, Sheng Lv, Fei Li, Xiao-Bo Wang, Bing-Hai Li, Qing-Ao Qin p. 3307-3314

Development and application of the helically coiled once-through steam generator module for dynamic simulation of nuclear hybrid energy system Keon Yeop Kim, Young Suk Bang p. 3315-3329

Research on void drift between rod bundle subchannels Shasha Liu, Zaiyong Ma, Bo Pang, Rui Zhang, Luteng Zhang, Quanyao Ren, Liangming Pan p. 3330-3334

Influence of aluminum and vanadium oxides on copper borate glass : a physical/radiological study Islam M. Nabil, Moamen G. El-Samrah, Mahmoud Y. Zorainy, H.Y. Zahran, Ahmed T. Mosleh, Ibrahim S. Yahia p. 3335-3346

(A) robust nano-indentation modeling method for ion-irradiated FCC single crystals using strain-gradient crystal plasticity theory and particle swarm optimization algorithm Van-Thanh Pham, Jong-Sung Kim p. 3347-3358

(A) study on the dose evaluation of critical groups for unrestricted reuse of the site after the decommissioning of Kori Unit 1 Hyung-Woo Seo, Gang-Woo Ryu, Young-Il Na, Chan-Geun Park, Jin-Won Son, Cheon-Woo Kim p. 3359-3368

Electricity mix scenarios simulation for Korean carbon neutrality in 2050 Pilhyeon Ju, Sungyeol Choi, Jongho Lee p. 3369-3377

Experimental examination on physical and radiation shielding features of boro-silicate glasses doped with varying amounts of BaO M.I. Sayyed, Abdelmoneim Saleh, Anjan Kumar, Fatma Elzahraa Mansour p. 3378-3384

Comparative analysis of modeling approaches for sulfide-induced corrosion of copper disposal canisters in a 3-dimensional domain Heejae Ju, Nakkyu Chae, Jung-Woo Kim, Hong Jang, Sungyeol Choi p. 3385-3396

Seismic fragility analysis of shield building considering strength ratio of mainshock and aftershocks Xue Zhang, Chunfeng Zhao, Lunhai Zhi, Rui Pang, Y.L. Mo p. 3397-3404

JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations Anže Pungerčič, Alireza Haghighat, Luka Snoj p. 3405-3424

Loading pattern optimization of VVER-1000 reactor core based on the discrete golden eagle optimization algorithm Sajjad Abbasi Fashami, Mahdi Zangian, Abdolhamid Minuchehr, Ahmadreza Zolfaghari p. 3425-3434

Assessment of MARS-KS prediction capability for natural circulation flow in passive heat removal system Jehee Lee, Youngjae Park, Seong-Su Jeon, Ju-Yeop Park, Hyoung Kyu Cho p. 3435-3449

(A) computational framework for drop time assessment of a control element assembly under fuel assembly deformations with fluid-structure interaction and frictional contact Dae-Guen Lim, Gil-Yong Lee, Nam-Gyu Park, Yong-Hwa Park p. 3450-3462

참고문헌 (44건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 Carbon free energy development and the role of small modular reactors: A review and decision framework for deployment in developing countries 미소장
2 Two-equation eddy-viscosity turbulence models for engineering applications 미소장
3 Multi-dimensional radiative transfer in non-isothermal cylindrical media with non-isothermal bounding walls 미소장
4 New reactor cavity cooling system having passive safety features using novel shape for HTGRs and VHTRs 미소장
5 Scaling analysis of PMR200 reactor cavity cooling system 미소장
6 Modeling of radiative heat transfer in an axisymmetric cylindrical enclosure with participating medium 미소장
7 Absorption by Infrared Bands of Carbon Dioxide Gas at Elevated Pressures and Temperatures* 미소장
8 Spectral emissivity of candidate alloys for very high temperature reactors in high temperature air environment 미소장
9 Scalar profiles and NO formation in laminar opposed-flow partially premixed methane/air flames 미소장
10 Heat transfer reduction between two finite concentric cylinders using radiation shields; Experimental and numerical studies 미소장
11 Computation fluid dynamics analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-Cooled Reactors 미소장
12 Evaluation of the Planck-mean absorption coefficients from HITRAN and HITEMP databases 미소장
13 Simple Benchmark Problems for Finite Element Weld Residual Stress Simulation 미소장
14 NuScale Plant Safety in Response to Extreme Events 미소장
15 The design and safety features of the IRIS reactor 미소장
16 Implications of small modular reactors for climate change mitigation 미소장
17 Preliminary accident analysis of Flexblue®underwater reactor 미소장
18 RCCS Experiments and Validation for High-Temperature Gas-Cooled Reactor 미소장
19 Thermophysical properties of stainless steels 미소장
20 Experimental analysis on passive residual heat removal in molten salt reactor using single cooling thimble test system 미소장
21 Investigation of radial heat transfer in a fixed-bed reactor: CFD simulations and profile measurements 미소장
22 Numerical simulation on heat transfer process in the reactor cavity of modular high temperature gas-cooled reactor 미소장
23 Experimental study on the heat transfer characteristics of fluoride salt in the new conceptual passive heat removal system of molten salt reactor 미소장
24 (Reference title not available) 미소장
25 Long-term decay heat removal in a submerged SMR 미소장
26 Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas 미소장
27 A flammability limit model for hydrogen-air-diluent mixtures based on heat transfer characteristics in flame propagation 미소장
28 Design of A scale-down experimental model for SFR reactor vault cooling system performance analyses 미소장
29 CFD modelling of buoyancy driven flows in enclosures with relevance to nuclear reactor safety 미소장
30 Convective and Radiative Heat Transfer in Molten Salts 미소장
31 Unsteady Natural Convection in a Cylindrical Containment Vessel (CIGMA) With External Wall Cooling: Numerical CFD Simulation 미소장
32 Improved prediction model for H2/CO combustion risk using a calculated non-adiabatic flame temperature model 미소장
33 Transport, constructability, and economic advantages of SMR modularization 미소장
34 Identification of the extinction mechanism of lean limit hydrogen flames based on Lewis number effect 미소장
35 Effect of layer-by-layer assembled carbon nanotube coatings on dropwise condensation heat transfer associated with non-condensable gas effect 미소장
36 Influence of seed layers on the reflectance of sputtered aluminum thin films 미소장
37 Investigations of non-gray/gray radiative heat transfer effect on natural convection in tall cavities at low operating temperature 미소장
38 Review of integration of small modular reactors in renewable energy microgrids 미소장
39 Investigation on Solar Absorption and Thermal Emittance of Al Films Deposited by Magnetron Sputtering 미소장
40 Coupled natural convection and radiation in a cubic cavity filled with an <i>air</i> - <i>H</i><SUB align="right">2<i>O</i> mixture in the presence of a heated obstacle 미소장
41 Radiation Models for Computational Fluid Dynamics Simulations of Photocatalytic Reactors 미소장
42 Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor 미소장
43 Development of an on-demand flooding safety system achieving long-term inexhaustible cooling of small modular reactors employing metal containment vessel 미소장
44 RADCAL -- a narrow-band model for radiation calculations in a combustion environment 미소장

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