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For: Yu H, Wang M, Cai R, Zhang D, Tian W, Qiu S, Su G. Development and validation of boron diffusion model in nuclear reactor core subchannel analysis. ANN NUCL ENERGY 2019;130:208-17. [DOI: 10.1016/j.anucene.2019.02.046] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
Number Cited by Other Article(s)
1
Zeng Y, Zhang Q, Chen H, Ming P, Liu S, Zeng C. Numerical investigation of the external emergency coolant transportation inside reactor annular down-comer. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109780] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/08/2023]
2
PLIF experiment and verification of boron mixed diffusion model driven by turbulence in nuclear reactor. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109682] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/18/2023]
3
CorTAF: A nuclear reactor core three-dimensional thermal-hydraulic characteristics analysis code based on OpenFOAM. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112209] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/12/2023]
4
Brayner de Oliveira Lira CA, de Andrade Lima FR, da Silva MAB. Causative process related method for the design of a reduced scale test facility for boron dispersion analysis in the pressurizer of SMRs. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104569] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 01/15/2023]
5
Zhang J, Chen N, Wang M, Tian W, Zhang J, Qiu S, Su G. The fouling and thermal hydraulic coupling study on the typical 5 × 5 rod bundle in PWRs. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104221] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
6
Ye L, Yu H, Wang M, Wang Q, Tian W, Qiu S, Su G. CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2021.07.047] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
7
Wang H, Zhang M, Li J, Wang J. Numerical study on CMT boron replenishment strategy for an AP1000 nuclear power unit. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.01.001] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
8
Zhang Q, Liu L, Xiao Y, Fu J, Gu H. Experimental study on the transverse mixing of 5 × 5 helical cruciform fuel assembly by wire mesh sensor. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108582] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/26/2023]
9
Chen G, Qian H, Li L, Yu Y, Zhang Z, Tian Z, Li X. Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2021.04.008] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
10
Chen G, Jiang H, Kang H, Ma R, Li L, Yu Y, Li X. Analysis of the performances of the CFD schemes used for coupling computation. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2021.01.006] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
11
Peng F, Su Q, Xing J, Lu D, Wang C, Gu H. Experimental study on flow distribution and mixing at the core inlet of double-loop small module reactor. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.108010] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
12
Wang H, Zhang M, Wang J, Tian Z. Numerical study of boron diffusion in CMT and related thermal fatigue near cold legs of an AP1000 nuclear power unit. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2020.103592] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
13
Yu H, Ju H, Wang M, Zhang J, Qiu S, Tian W, Su G. Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107659] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
14
Distributed-parallel CFD computation for all fuel assemblies in PWR core. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107340] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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