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Wu S, Zhang Y, Wang D, Ge K, Tian W, Qiu S, Su G. Study on the safety characteristics of molten corium in-vessel retention of annular fuel core. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109750] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/24/2023]
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Liu S, Liu R, Qiu C. CAMPUS-ANNULAR: Preliminary multiphysics modeling of annular fuel performance under normal operating and accident conditions. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104430] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Saffari A, Esmaili H. Development of subchannel thermal-hydraulic analysis code for dual cooled annular fuel. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104298] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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He Y, Niu Y, Xiang F, Wu Y, Zhang J, Su G, Tian W, Qiu S. Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111810] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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Development of thermal hydraulic analysis code of annular fuel under flow blockage condition. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107962] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Esmaili H, Kazeminejad H, Khalafi H, Mirvakili S. Subchannel analysis of annular fuel assembly using the preconditioned Jacobian-free Newton Krylov methods. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107616] [Citation(s) in RCA: 9] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Prediction of temperature distribution in annular fuels using orthogonal collocation method. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.06.015] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Hassan IA, Badawi AA, El Saghir A, Shaat MK. Viability of uranium nitride (UN) as annular fuel for AP-1000. PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2018.09.020] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Che Y, Pastore G, Hales J, Shirvan K. Modeling of Cr2O3-doped UO2 as a near-term accident tolerant fuel for LWRs using the BISON code. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.07.015] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Development of high thermal conductivity UO2–Th heterogeneous fuel. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.06.012] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Rhee YW, Kim DJ, Kim JH, Yang JH, Kim KS. Rod-Inserted Sintering of Annular Pellets for Dual-Cooled Annular Fuel. NUCL TECHNOL 2017. [DOI: 10.13182/nt13-a19868] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Young Woo Rhee
- Korea Atomic Energy Research Institute, LWR Fuel Technology Division Daejeon 305-353, Republic of Korea
| | - Dong Joo Kim
- Korea Atomic Energy Research Institute, LWR Fuel Technology Division Daejeon 305-353, Republic of Korea
| | - Jong Hun Kim
- Korea Atomic Energy Research Institute, LWR Fuel Technology Division Daejeon 305-353, Republic of Korea
| | - Jae Ho Yang
- Korea Atomic Energy Research Institute, LWR Fuel Technology Division Daejeon 305-353, Republic of Korea
| | - Keon Sik Kim
- Korea Atomic Energy Research Institute, LWR Fuel Technology Division Daejeon 305-353, Republic of Korea
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Shirvan K, Kazimi M. Superheated Water-Cooled Small Modular Underwater Reactor Concept. NUCLEAR ENGINEERING AND TECHNOLOGY 2016. [DOI: 10.1016/j.net.2016.06.003] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Shirvan K, Ballinger R, Buongiorno J, Forsberg C, Kazimi M, Todreas N. Technology Selection for Offshore Underwater Small Modular Reactors. NUCLEAR ENGINEERING AND TECHNOLOGY 2016. [DOI: 10.1016/j.net.2016.06.002] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Ghazanfari V, Talebi M, Khorsandi J, Abdolahi R. Effects of water based Al2O3, TiO2, and CuO nanofluids as the coolant on solid and annular fuels for a typical VVER-1000 core. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2016.05.007] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Ghazanfari V, Talebi M, Khorsandi J, Abdolahi R. Thermal–hydraulic modeling of water/Al2O3 nanofluid as the coolant in annular fuels for a typical VVER-1000 core. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2015.11.008] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Groeneveld D, Leung L, Park J. Overview of methods to increase dryout power in CANDU fuel bundles. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.03.010] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Duarte JP, Rivero JJ, Melo PFFE, Alvim ACM. Coupling of a Lumped Parameter and a Finite Difference Model for Estimation of a Reactivity-Induced Transient in a PWR with Annular Fuel Rods. NUCL TECHNOL 2014. [DOI: 10.13182/nt12-149] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- J. P. Duarte
- Federal University of Rio de Janeiro, Polytechnic School, Department of Nuclear Engineering, Av. Horácio Macedo 2030, Bloco G, Sala 206, Cidade Universitária, 21941-914 Rio de Janeiro, RJ, Brazil
| | - J. J. Rivero
- Federal University of Rio de Janeiro, Polytechnic School, Department of Nuclear Engineering, Av. Horácio Macedo 2030, Bloco G, Sala 206, Cidade Universitária, 21941-914 Rio de Janeiro, RJ, Brazil
| | - P. F. Frutuoso E Melo
- Federal University of Rio de Janeiro, COPPE, Graduate Engineering Program, Av. Horácio Macedo 2030, Bloco G, Sala 206, Cidade Universitária, 21941-914 Rio de Janeiro, RJ, Brazil
| | - A. C. M. Alvim
- Federal University of Rio de Janeiro, COPPE, Graduate Engineering Program, Av. Horácio Macedo 2030, Bloco G, Sala 206, Cidade Universitária, 21941-914 Rio de Janeiro, RJ, Brazil
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Amin Mozafari M, Faghihi F. Design of annular fuels for a typical VVER-1000 core: Neutronic investigation, pitch optimization and MDNBR calculation. ANN NUCL ENERGY 2013. [DOI: 10.1016/j.anucene.2013.04.035] [Citation(s) in RCA: 19] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Parameter study for manufacturing an inner and outer cladding tube used in dual-cooled annular fuel. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2012.03.036] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Shin CH, Chun TH, Oh DS, In WK. Thermal hydraulic performance assessment of dual-cooled annular nuclear fuel for OPR-1000. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.12.010] [Citation(s) in RCA: 41] [Impact Index Per Article: 3.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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RHEE YW, KIM DJ, KIM JH, YANG JH, KIM KS, KANG KW, SONG KW. Fabrication of Sintered Annular Fuel Pellet for HANARO Irradiation Test. J NUCL SCI TECHNOL 2010. [DOI: 10.1080/18811248.2010.9711964] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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