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This paper presents the construction results and design of the UNIST Reactor Innovation platform for small modular reactors as a versatile testbed for exploring innovative technologies. The platform uses simulant fluids to simulate the thermal-hydraulic behavior of a reference small modular reactor design, allowing for cost-effective design modifications. Scaling analysis results for single and two-phase natural circulation flows are outlined based on the three-level scaling methodology. The platform’s capability to simulate natural circulation behavior was validated through performance calculations using the 1-D system thermal-hydraulic code-based calculation. The strategies for evaluating cutting-edge technologies, such as the integration of a solid oxide electrolysis cell for hydrogen production into a small modular reactor, are presented. To overcome experimental limitations, the hardware-in-the-loop technique is proposed as an alternative, enabling real-time simulation of physical phenomena that cannot be implemented within the experimental facility’s hardware. Overall, the proposed versatile innovation platform is expected to provide valuable insights for advancing research in the field of small modular reactors and nuclear-based hydrogen production.

권호기사

권호기사 목록 테이블로 기사명, 저자명, 페이지, 원문, 기사목차 순으로 되어있습니다.
기사명 저자명 페이지 원문 목차
Nodal method for handling irregularly deformed geometries in hexagonal lattice cores Seongchan Kim, Han Gyu Joo, Hyun Chul Lee p. 772-784

(The) development of a fuel lifecycle reactivity control strategy for a generic micro high temperature reactor Seddon Atkinson, Takeshi Aoki p. 785-792

Thermal study of the emergency draining tank of molten salt reactor C. Péniguel p. 793-802

PASTELS project : overall progress of the project on experimental and numerical activities on passive safety systems Michaël Montout, Christophe Herer, Joonas Telkkä, PASTELS consortium members p. 803-811

Adsorption behavior of platinum-group metals and co-existing metal ions from simulated high-level liquid waste using HONTA and Crea impregnated adsorbent Naoki Osawa, Seong-Yun Kim, Masahiko Kubota, Hao Wu, Sou Watanabe, Tatsuya Ito, Ryuji Nagaishi p. 812-818

SSC risk significance in risk-informed, performance-based licensing of non-LWRs James C. Lin p. 819-823

(The) SPIZWURZ project : experimental investigations and modeling of the behavior of hydrogen in zirconium alloys under long-term dry storage conditions Mirco Grosse, Felix Boldt, Michel Herm, Conrado Roessger, Juri Stuckert, Sarah Weick, Daniel Nahm p. 824-831

Comparison on safety features among HTGR’s reactor cavity cooling systems (RCCSs) Kuniyoshi Takamatsu, Shumpei Funatani p. 832-845

Development of FEMAXI-ATF for analyzing PCMI behavior of SiC cladded fuel under power ramp conditions Yoshihiro Kubo, Akifumi Yamaji p. 846-854

(A) central facility concept for nuclear microreactor maintenance and fuel cycle management Faris Fakhry, Jacopo Buongiorno, Steve Rhyne, Benjamin Cross, Paul Roege, Bruce Landrey p. 855-865

Assessment of CATHARE code against DEC-A upper head SBLOCA experiments Anis Bousbia Salah p. 866-872

SIMMER-Ⅳ application to safety assessment of severe accident in a small SFR H. Tagami, Y. Tobita p. 873-879

SiRENE : a new generation of engineering simulator for real-time simulators at EDF David Pialla, Stéphanie Sala, Yann Morvan, Lucie Dreano, Denis Berne, Eléonore Bavoil p. 880-885

Evaluation of temperatures and flow areas of the phebus test FPT0 Koji Nishida, Naoki Sano, Seitaro Sakurai, Michio Murase p. 886-892

Fundamental evaluation of hydrogen behavior in sodium for sodium-water reaction detection of sodium-cooled fast reactor Tomohiko Yamamoto, Atsushi Kato, Masato Hayakawa, Kazuhito Shimoyama, Kuniaki Ara, Nozomu Hatakeyama, Kanau Yamauchi, Yuhei Eda, Masahiro Yui p. 893-899

Burnable absorber design study for a passively-cooled molten salt fast reactor Nariratri Nur Aufanni, Eunhyug Lee, Taesuk Oh, Yonghee Kim p. 900-906

Multi-batch core design study for innovative small modular reactor based on centrally-shielded burnable absorber Steven Wijaya, Xuan Ha Nguyen, Yunseok Jeong, Yonghee Kim p. 907-915

Sensitivity of a control rod worth estimate to neutron detector position by time-dependent Monte Carlo simulations of the rod drop experiment Jong Min Park, Cheol Ho Pyeon, Hyung Jin Shim p. 916-921

Core design study of the Wielenga innovation static salt reactor (WISSR) T. Wielenga, W.S. Yang, I. Khaleb p. 922-932

Cross section generation for a conceptual horizontal, compact high temperature gas reactor Junsu Kang, Volkan Seker, Andrew Ward, Daniel Jabaay, Brendan Kochunas, Thomas Downar p. 933-940

Radiation effect on the corrosion of disposal canister materials Minsoo Lee, Junhyuk Jang, Jin Seop Kim p. 941-948

Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor Hyo Jun An, Jae Hyung Park, Chang Hyun Song, Jeong Ik Lee, Yonghee Kim, Sung Joong Kim p. 949-958

Analysis of forced convection in the HTTU experiment using numerical codes M.C. Potgieter, C.G. du Toit p. 959-965

Idaho national laboratory to demonstrate collaboration first versus competition to accelerate achieving a secure clean energy future by 2031 Jhansi Kandasamy, Elizabeth Brunner p. 966-972

Analysis of the thermal-mechanical behavior of SFR fuel pins during fast unprotected transient overpower accidents using the GERMINAL fuel performance code Vincent Dupont, Victor Blanc, Thierry Beck, Marc Lainet, Pierre Sciora p. 973-979

Transient full core analysis of PWR with multi-scale and multi-physics approach Jae Ryong Lee, Han Young Yoon, Ju Yeop Park p. 980-992

(The) TANDEM euratom project : context, objectives and workplan C. Vaglio-Gaudard, M.T. Dominguez Bautista, M. Frignani, M. Fütterer, A. Goicea, E. Hanus, T. Hollands, C. Lombardo, S. Lorenzi, J. Miss ... [et al.] p. 993-1001

Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor Won Jun Choi, Jae Hyung Park, Juhyeong Lee, Jihun Im, Yunsik Cho, Yonghee Kim, Sung Joong Kim p. 1002-1012

Rare earth removal from pyroprocessing fuel product for preparing MSR fuel Dalsung Yoon, Seungwoo Paek, Chang Hwa Lee p. 1013-1021

Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion Kwangho Ju, Jaehyun Ryu, Yonghee Kim p. 1022-1028

NUWARD SMR safety approach and licensing objectives for international deployment D. Francis, S. Beils p. 1029-1036

Design and construction of fluid-to-fluid scaled-down small modular reactor platform : as a testbed for the nuclear-based hydrogen production Ji Yong Kim, Seung Chang Yoo, Joo Hyung Seo, Ji Hyun Kim, In Cheol Bang p. 1037-1051

Development of scaling approach based on experimental and CFD data for thermal stratification and mixing induced by steam injection through spargers Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov p. 1052-1065

Overview of separate effect and integral system tests on the passive containment cooling system of SMART100 Jin-Hwa Yang, Tae-Hwan Ahn, Hong Hyun Son, Jin Su Kwon, Hwang Bae, Hyun-Sik Park, Kyoung-Ho Kang p. 1066-1080

Numerical analysis of the venturi flowmeter in the liquid lead-bismuth eutectic circuit after long-term operation Zhichao Zhang, Rafael Macian-Juan, Xiang Wang p. 1081-1090

Thermal dehydration tests of FLiNaK salt for thermal-hydraulic experiments Shuai Che, Sheng Zhang, Adam Burak, Xiaodong Sun p. 1091-1099

Nuclear waste attributes of near-term deployable small modular reactors Taek K. Kim, L. Boing, B. Dixon p. 1100-1107

Consequence-based security for microreactors Emile Gateau, Neil Todreas, Jacopo Buongiorno p. 1108-1115

Conceptual design of a MW heat pipe reactor Yunqin Wu, Youqi Zheng, Qichang Chen, Jinming Li, Xianan Du, Yongping Wang, Yushan Tao p. 1116-1123

참고문헌 (48건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 Pressurized Water Reactor Inherent Core Protection by Primary System Thermohydraulics 미소장
2 KAERI Integral Effect Test Program and the ATLAS Design 미소장
3 Hybrid heat pipe based passive in-core cooling system for advanced nuclear power plant 미소장
4 NuScale small modular reactor for Co-generation of electricity and water 미소장
5 Fluid-to-fluid scaling for a gravity- and flashing-driven natural circulation loop 미소장
6 The effects of break location on PWR small break LOCA: Experimental study at the ROSA-IV LSTF 미소장
7 Inherently Safe Reactors and a Second Nuclear Era 미소장
8 Analyses of the OSU-MASLWR Experimental Test Facility 미소장
9 The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA) 미소장
10 Experimental investigations on the heat transfer characteristics in a natural circulation loop for an integral type reactor 미소장
11 PIUS - status and perspectives 미소장
12 (Reference title not available) 미소장
13 Scaling of two-phase flow transients using reduced pressure system and simulant fluid 미소장
14 Technological development of hydrogen production by solid oxide electrolyzer cell (SOEC) 미소장
15 Scaling laws for thermal-hydraulic system under single phase and two-phase natural circulation 미소장
16 Scaling analysis for the OSU AP600 test facility (APEX) 미소장
17 Experimental and theoretical studies on density wave instabilities in helically coiled tubes 미소장
18 NuScale Plant Safety in Response to Extreme Events 미소장
19 An integrated structure and scaling methodology for severe accident technical issue resolution: Development of methodology 미소장
20 Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors 미소장
21 Cogeneration: An option to facilitate load following in Small Modular Reactors 미소장
22 Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant 미소장
23 Experimental study on accident transients and flow instabilities in a PWR-type small modular reactor 미소장
24 Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal 미소장
25 Autonomous operation algorithm for safety systems of nuclear power plants by using long-short term memory and function-based hierarchical framework 미소장
26 Load-following with nuclear power: Market effects and welfare implications 미소장
27 Experimental flow visualization study using particle image velocimetry in a helical coil steam generator with changing lateral pitch geometry 미소장
28 CAREM-25: A Safe Innovative Small Nuclear Power Plant 미소장
29 High-resolution high-speed void fraction measurements in helically coiled tubes using X-ray radiography 미소장
30 Experimental measurements of turbulent flows in a rod bundle with a 3-D printed channel-type spacer grid 미소장
31 Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform 미소장
32 Algorithm for Autonomous Power-Increase Operation Using Deep Reinforcement Learning and a Rule-Based System 미소장
33 The PIUS Pressurized Water Reactor: Aspects of Plant Operation and Availability 미소장
34 Carbon neutrality: Toward a sustainable future 미소장
35 Dynamic simulation of a novel nuclear hybrid energy system with large-scale hydrogen storage in an underground salt cavern 미소장
36 Review of integration of small modular reactors in renewable energy microgrids 미소장
37 Net Zero by 2050: A Roadmap for the Global Energy Sector 미소장
38 SMART: The First Licensed Advanced Integral Reactor 미소장
39 Experimental investigation on flashing-induced flow instability in a natural circulation scaled-down test facility 미소장
40 A nuclear‑hydrogen hybrid energy system with large-scale storage: A study in optimal dispatch and economic performance in a real-world market 미소장
41 Design of a Test Article and Test Facility to Investigate Flow-Induced Vibration of a Helical Coil Steam Generator 미소장
42 Real-Time Simulation of a Small Modular Reactor in-the-Loop within Nuclear-Renewable Hybrid Energy Systems 미소장
43 Deep-learning-based system-scale diagnosis of a nuclear power plant with multiple infrared cameras 미소장
44 Development of fault diagnosis for nuclear power plant using deep learning and infrared sensor equipped UAV 미소장
45 Autonomous control model for emergency operation of small modular reactor 미소장
46 Nuclear-Renewable Hybrid Energy System with Load Following for Fast Charging Stations 미소장
47 Thermal-Hydraulic Research Supporting the Development of SMART 미소장
48 Dual-fluid topology optimization of printed-circuit heat exchanger with low-pumping-power design 미소장

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