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El Kheiri O, Kabach O, Chetaine A. Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104680] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 04/07/2023]
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2
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Prospects for additive manufacturing of nuclear fuel forms. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2022.104493] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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3
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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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Zayermohammadi Rishehri H, Zaidabadi Nejad M. Design and Neutronic, Thermal-Hydraulic Analysis of DSCF Assembly for a SMR and Investigation of the Effect on the Thermal Power Uprate. NUCL TECHNOL 2022. [DOI: 10.1080/00295450.2022.2120319] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/14/2022]
Affiliation(s)
- Hossein Zayermohammadi Rishehri
- Graduate University of Advanced Technology, Faculty of Sciences and Modern Technologies, Department of Nuclear Engineering, Haftbagh Street, 7631818356, Kerman, Iran
| | - Majid Zaidabadi Nejad
- Graduate University of Advanced Technology, Faculty of Sciences and Modern Technologies, Department of Nuclear Engineering, Haftbagh Street, 7631818356, Kerman, Iran
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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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Zayermohammadi Rishehri H, Zaidabadi Nejad M. Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC. KERNTECHNIK 2022. [DOI: 10.1515/kern-2021-1012] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
Abstract
Abstract
Power upgrade in nuclear reactors has been identified as one of the least costly options. This article focuses on how to further increase the thermal power and the possibility of using internally and externally cooled (I&EC) fuels instead of the solid fuels in the core of a Small Modular Reactor (SMR). In hence, The NuScale is chosen as the reference SMR. The core of NuScale is designed based on the use of a new 12 × 12 I&EC fuel assembly. This study is conducted throughout neutronic/thermal-hydraulic analysis. And many essential neutronic and thermal-hydraulic parameters such as variations of effective multiplication factor as a function of the pitch, neutron flux, power peaking factors, DNBRs and maximum temperature of the fuel were obtained. As one of the most important results of the analysis, I&EC fuel shows a sufficient margin available on DNBR and fuel pellet temperature compared with cylindrical solid fuel. The margin amount seems accommodating a 183% power-uprate seems viable. Also, the fuels axial temperature at different power levels were analyzed, and it was found that the proposed fuel at high power levels has a low peak temperature.
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Affiliation(s)
- Hossein Zayermohammadi Rishehri
- Department of Nuclear Engineering, Faculty of Sciences and Modern Technologies , Graduate University of Advanced Technology , Haftbagh St, Postal Code: 7631818356 , Kerman , Iran
| | - Majid Zaidabadi Nejad
- Department of Nuclear Engineering, Faculty of Sciences and Modern Technologies , Graduate University of Advanced Technology , Haftbagh St, Postal Code: 7631818356 , Kerman , Iran
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Core design and neutronic study on small reactor with advanced fuel designs. NUCLEAR MATERIALS AND ENERGY 2021. [DOI: 10.1016/j.nme.2021.101068] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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8
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Yang J, Yuan L. Pressure drop experiment with externally and internally cooled annular fuel bundles. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111528] [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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Akter Y, Hossain Sahadath M, Reza F. Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111339] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Rahnama Z, Ansarifar G. Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational fluid dynamic (CFD) modeling via neutronic and thermal-hydraulics coupling. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103796] [Citation(s) in RCA: 6] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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11
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Deng Y, Liu M, Qiu B, Yin Y, Gong X, Huang X, Pang B, Li Y. Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2020.06.025] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Xu Z, Liu Y, Wang B. Simulation and optimization design of fuel rod in pressurized water fuel assemblies. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110856] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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13
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Kohse G, Carpenter D, Yuan Y, Hejzlar P, Kazimi M. Irradiation Testing of High-Power-Density Vibropacked Annular Fuel. NUCL TECHNOL 2017. [DOI: 10.13182/nt07-a3889] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Gordon Kohse
- Massachusetts Institute of Technology Department of Nuclear Science and Engineering, Nuclear Reactor Laboratory and Center for Advanced Nuclear Energy Systems, Cambridge, Massachusetts 02139-4307
| | - David Carpenter
- Massachusetts Institute of Technology Department of Nuclear Science and Engineering, Nuclear Reactor Laboratory and Center for Advanced Nuclear Energy Systems, Cambridge, Massachusetts 02139-4307
| | - Yi Yuan
- Massachusetts Institute of Technology Department of Nuclear Science and Engineering, Nuclear Reactor Laboratory and Center for Advanced Nuclear Energy Systems, Cambridge, Massachusetts 02139-4307
| | - Pavel Hejzlar
- Massachusetts Institute of Technology Department of Nuclear Science and Engineering, Nuclear Reactor Laboratory and Center for Advanced Nuclear Energy Systems, Cambridge, Massachusetts 02139-4307
| | - Mujid Kazimi
- Massachusetts Institute of Technology Department of Nuclear Science and Engineering, Nuclear Reactor Laboratory and Center for Advanced Nuclear Energy Systems, Cambridge, Massachusetts 02139-4307
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Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.02.019] [Citation(s) in RCA: 20] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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15
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Deng Y, Wu Y, Zhang D, Tian W, Qiu S, Su G. Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.03.021] [Citation(s) in RCA: 28] [Impact Index Per Article: 3.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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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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17
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In WK, Shin CH, Kwack YK, Lee CY. Measurement and CFD calculation of spacer loss coefficient for a tight-lattice fuel bundle. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2014.12.021] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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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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An experimental investigation on turbulent flow mixing in a simulated 3×3 dual-cooled annular fuel bundle using particle image velocimetry. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.03.013] [Citation(s) in RCA: 21] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Lee CY, Shin CH, In WK. Pressure drop in dual-cooled annular and cylindrical solid fuel assemblies for pressurized water reactor. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2012.05.039] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Memmott M, Buongiorno J, Hejzlar P. An Evaluation of the Annular Fuel and Bottle-Shaped Fuel Concepts for Sodium Fast Reactors. NUCL TECHNOL 2011. [DOI: 10.13182/nt11-a11545] [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)
- Matthew Memmott
- Massachusetts Institute of Technology, Nuclear Science and Engineering Department 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Jacopo Buongiorno
- Massachusetts Institute of Technology, Nuclear Science and Engineering Department 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Pavel Hejzlar
- Massachusetts Institute of Technology, Nuclear Science and Engineering Department 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
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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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