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1
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Wu S, Wan J, Chen Z, Liao L, Xiao K, Wang P. LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies. NUCL SCI ENG 2022. [DOI: 10.1080/00295639.2022.2123204] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Affiliation(s)
- Shifa Wu
- Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, and Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi’an Jiaotong University, Xi’an City 710049, China
| | - Jiashuang Wan
- Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, and Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi’an Jiaotong University, Xi’an City 710049, China
| | - Zhi Chen
- Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu City 610213, China
| | - Longtao Liao
- Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu City 610213, China
| | - Kai Xiao
- Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu City 610213, China
| | - Pengfei Wang
- Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, and Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi’an Jiaotong University, Xi’an City 710049, China
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2
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Zhao F, Zou S, Xu S, Wang J, Xu T, Tang D. Safety analysis of marine nuclear reactor in severe accident with dynamic fault trees based on cut sequence method. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.08.014] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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3
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Analysis of the natural circulation system characteristics with fuel rods under motion conditions. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109224] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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4
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5
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Wang P, Jiang Q, Zhang J, Wan J, Wu S. A fuzzy fault accommodation method for nuclear power plants under actuator stuck faults. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108674] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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6
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Wang D, Jiang J, Liu Y. Relaxation of the requirements on loop height and heat transfer area of a passive heat removal system in integral SMR using a self-powered booster. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108539] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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7
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Bae H, Ryu SU, Yang JH, Jeon BG, Bang YG, Yi SJ, Park HS. Evaluation of thermal–hydraulic characteristics of reactor coolant system and helically coiled steam generator based on performance tests with SMART-ITL. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111392] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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8
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Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.108096] [Citation(s) in RCA: 7] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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9
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Experimental correlation for critical heat flux in helical coils. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110759] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/13/2022]
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10
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Code improvement, separate-effect validation, and benchmark calculation for thermal-hydraulic analysis of helical coil once-through steam generator. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107333] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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11
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Design concepts of supercritical water-cooled reactor (SCWR) and nuclear marine vessel: A review. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103320] [Citation(s) in RCA: 16] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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12
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Hou Y, Wang M, Zhang J, Qiu S, Su G, Tian W. Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR). PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2019.03.020] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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13
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Parametric neutronics analyses of lattice geometry and coolant candidates for a soluble-boron-free civil marine SMR core using micro-heterogeneous duplex fuel. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.01.037] [Citation(s) in RCA: 12] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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14
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Small modular reactor core design for civil marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.03.005] [Citation(s) in RCA: 26] [Impact Index Per Article: 5.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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15
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Wei X, Qing J, Wan J, Wang P, Zhao F. A master-slave control strategy of the multi-modular SMR. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.11.033] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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16
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Ondir Freire L, de Andrade DA. Economically Feasible Mobile Nuclear Power Plant for Merchant Ships and Remote Clients. NUCL TECHNOL 2018. [DOI: 10.1080/00295450.2018.1546067] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
Affiliation(s)
- Luciano Ondir Freire
- Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), Center of Nuclear Engineering, Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, São Paulo, Brazil
| | - Delvonei Alves de Andrade
- Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), Center of Nuclear Engineering, Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, São Paulo, Brazil
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17
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Xia G, Yuan Y, Peng M, Lv X, Sun L. Numerical studies of a helical coil once-through steam generator. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.05.025] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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18
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Wan J, Wang P, Wu S, Zhao F. Controller design and optimization of reactor power control system for ASPWR. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2017.06.006] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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19
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Chung YJ, Kim HK, Kim HC, Zee SQ. A Conservative Analysis Methodology for a Steam-Line-Break Accident of the SMART-P Plant. NUCL TECHNOL 2017. [DOI: 10.13182/nt06-a3688] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Young-Jong Chung
- Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon 305-600, Republic of Korea
| | - Hee-Kyung Kim
- Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon 305-600, Republic of Korea
| | - Hee-Cheol Kim
- Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon 305-600, Republic of Korea
| | - Sung-Quun Zee
- Korea Atomic Energy Research Institute P.O. Box 105, Yuseong, Daejeon 305-600, Republic of Korea
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20
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Xia G, Su G, Peng M. Analysis of natural circulation operational characteristics for integrated pressurized water reactor. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.01.032] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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21
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Du X, Xia G, He L. Operation characteristic of Integrated Pressurized Water Reactor under coordination control scheme. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2014.08.066] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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22
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Marcel C, Acuña F, Zanocco P, Delmastro D. Stability of self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The stability performance of the CAREM-25 reactor. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.08.057] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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23
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Wang Z, Tian W, Su G, Qiu S, Zhao L, Zuo Q, Wu Y, Zhang D. Development of a thermal hydraulic code for an integral reactor. PROGRESS IN NUCLEAR ENERGY 2013. [DOI: 10.1016/j.pnucene.2013.04.010] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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24
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Marcel C, Furci H, Delmastro D, Masson V. Phenomenology involved in self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The thermal–hydraulics of the CAREM-25 reactor. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2012.09.005] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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25
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Wu Y, Su G, Qiu S, Tian W. Development of a thermal–hydraulic analysis software for a passive residual heat removal system. ANN NUCL ENERGY 2012. [DOI: 10.1016/j.anucene.2012.05.012] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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26
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Garcia RF, Carril JC, Catoira AD, Gomez JR. Efficiency enhancement of GT-MHRs applied on ship propulsion plants. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2012.06.013] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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27
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Wang Z, Tian W, Wu Y, Qiu S, Su G. Numerical study on annular tube once-through steam generator using compressible flow model. ANN NUCL ENERGY 2012. [DOI: 10.1016/j.anucene.2011.07.009] [Citation(s) in RCA: 25] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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28
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Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2009. [DOI: 10.1155/2009/473795] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary side of the steam generator, for an integral pressurized water reactor is presented in this paper. Three-interknited natural circulation loops are adopted by this PRHRS to remove the residual heat of the reactor core after a reactor trip. Based on the one-dimensional model and a simulation code (SCPRHRS), the transient behaviors of the PRHRS as well as the effects of the height difference between the steam generator and the heat exchanger and the heat transfer area of the heat exchanger are studied in detail. Through the calculation analysis, it is found that the calculated parameter variation trends are reasonable. The higher height difference between the steam generator and the residual heat exchanger and the larger heat transfer area of the residual heat exchanger are favorable to the passive residual heat removal system.
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Odano N, Ishida T. Radiation safety assessment of a system of small reactors for distributed energy. RADIATION PROTECTION DOSIMETRY 2005; 115:95-9. [PMID: 16381690 DOI: 10.1093/rpd/nci208] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [MESH Headings] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 05/05/2023]
Abstract
A passively safe small reactor for a distributed energy system, PSRD, is an integral type of light-water reactor with a thermal output of 100 or 300 MW aimed to be used for supplying district heat, electricity to small grids, and so on. Candidate locations for the PSRD as a distributed energy source are on-ground, deep underground, and in a seaside pit in the vicinity of the energy consumption area. Assessments of the radiation safety of a PSRD were carried out for three cases corresponding to normal operation, shutdown and a hypothetical postulated accident for several siting candidates. Results of the radiation safety assessment indicate that the PSRD design has sufficient shielding performance and capability and that the exposure to the general public is very low in the case of a hypothetical accident.
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Affiliation(s)
- N Odano
- Department of Maritime Safety, National Maritime Research Institute, Mitaka, Tokyo 181-0004, Japan.
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Chung YJ, Kim SH, Kim HC. Thermal hydraulic analysis of SMART for heat removal transients by a secondary system. NUCLEAR ENGINEERING AND DESIGN 2003. [DOI: 10.1016/s0029-5493(03)00193-6] [Citation(s) in RCA: 26] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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31
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YORITSUNE T, ISHIDA T, IMAYOSHI S. In-vessel Type Control Rod Drive Mechanism Using Magnetic Force Latching for a Very Small Reactor. J NUCL SCI TECHNOL 2002. [DOI: 10.1080/18811248.2002.9715276] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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32
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ISHIDA T, IMAYOSHI S, YORITSUNE T, NUNOKAWA H, OCHIAI MA, ISHIZAKA Y. Development of In-vessel Type Control Rod Drive Mechanism for Marine Reactor. J NUCL SCI TECHNOL 2001. [DOI: 10.1080/18811248.2001.9715067] [Citation(s) in RCA: 12] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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