Development of LWR Fuel Performance Analysis Codes
This paper is to cover brief history of the development of LWR fuel performance analysis codes in Japan. This includes the FEMAXI-III code which calculates local stress and strain of the cladding at power ramp due to the pellet cladding mechanical interaction (PCMI) using axisymmetric finite element...
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Published in | Journal of nuclear science and technology Vol. 30; no. 1; pp. 1 - 17 |
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Main Author | |
Format | Journal Article |
Language | English |
Published |
Tokyo
Taylor & Francis Group
01.01.1993
Atomic Energy Society of Japan Taylor & Francis Ltd |
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Abstract | This paper is to cover brief history of the development of LWR fuel performance analysis codes in Japan. This includes the FEMAXI-III code which calculates local stress and strain of the cladding at power ramp due to the pellet cladding mechanical interaction (PCMI) using axisymmetric finite element method. From this code some improved codes were developed, such as FEMAXI IV, IRON and EIMUS. The FEMAXI-IV is developed by J AERI to add capacity of transient analysis and che IRON code was developed by Shikoku Electric Power Co. to analyze fuel reliability at load following operation and the EIMUS code was developed by CRIEPI for high burnup analysis. The major objective and contents of adapted submodels in these codes are presented with some calculational results. The future development and utilization of the codes, especially for performance analyses at high burnup, will be briefly discussed. |
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AbstractList | this paper is to cover brief history of the development of LWR fuel performance analysis codes in Japan. This includes the FEMAXI-III code which calculates local stress and strain of the cladding at power ramp due to the pellet cladding mechanical interaction (PCMI) using axisymmetric finite element method. From this code some improved codes were developed, such as FEMAXI-IV, IRON and EIMUS. The FEMAXI-IV is developed by JAERI to add capacity of transient analysis and the IRON code was developed by Shikoku Electric Power Co. to analyze fuel reliability at load following operation and the EIMUS code was developed by CRIEPI for high burnup analysis. The major objective and contents of adapted submodels in these codes are presented with some calculational results. The future development and utilization of the codes, especially for performance analyses at high burnup, will be briefly discussed. This paper is to cover brief history of the development of LWR fuel performance analysis codes in Japan. This includes the FEMAXI-III code which calculates local stress and strain of the cladding at power ramp due to the pellet cladding mechanical interaction (PCMI) using axisymmetric finite element method. From this code some improved codes were developed, such as FEMAXI IV, IRON and EIMUS. The FEMAXI-IV is developed by J AERI to add capacity of transient analysis and che IRON code was developed by Shikoku Electric Power Co. to analyze fuel reliability at load following operation and the EIMUS code was developed by CRIEPI for high burnup analysis. The major objective and contents of adapted submodels in these codes are presented with some calculational results. The future development and utilization of the codes, especially for performance analyses at high burnup, will be briefly discussed. |
Author | KINOSHITA, Motoyasu |
Author_xml | – sequence: 1 givenname: Motoyasu surname: KINOSHITA fullname: KINOSHITA, Motoyasu organization: Nuclear Fuel Section, Nuclear Engineering Department , Central Research Institute of Electric Power Industry |
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Copyright | Copyright Taylor & Francis Group, LLC 1993 1994 INIST-CNRS Copyright Japan Science and Technology Agency 1993 |
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Keywords | Performance evaluation Finite element method Nuclear fuel Software Clad Light water reactor |
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References | Mogard H. (CIT0024) 1979 Okubo T. (CIT0008) 1982 Kinoshita M. (CIT0002) 1980; 56 Nakajima T. (CIT0012) Nakajima T. (CIT0011) 1987; 144 Matzke H.J. (CIT0020) 1980 Iwano Y. (CIT0003) 1980; 56 CIT0016 Mogard H. (CIT0025) 1984 Nakajima T. (CIT0009) 1985 CIT0018 Joon K. (CIT0001) 1976 CIT0019 Ichikawa M. (CIT0007) 1980; 149 Nakajima T. (CIT0013) 1988 CIT0021 CIT0023 CIT0022 Matsui T. (CIT0015) 1987; 54 Ito K. (CIT0017) 1980; 56 Kameyama T. (CIT0028) 1990 Nakajima T. (CIT0010) 1985; 88 Knudsen P. (CIT0026) 1989 CIT0005 CIT0027 CIT0004 Kinoshita M. (CIT0014) 1988 Ito K. (CIT0006) 1981; 2 |
References_xml | – year: 1976 ident: CIT0001 publication-title: Proc. of Specialist Mtg. on the Behavior of Water Reactor Fuel Elements under Accident Conditions, Spatiend, Norway, Sep. 13–16 contributor: fullname: Joon K. – ident: CIT0021 – year: 1984 ident: CIT0025 publication-title: Studsvik Energiteknik AB. STSR-53 contributor: fullname: Mogard H. – volume: 56 start-page: 41 year: 1980 ident: CIT0003 publication-title: Nucl. Eng. Des. doi: 10.1016/0029-5493(80)90166-1 contributor: fullname: Iwano Y. – year: 1979 ident: CIT0024 publication-title: Studsvik Energiteknik AB. STSR-53 contributor: fullname: Mogard H. – volume-title: RISO-TEGP-R29 year: 1989 ident: CIT0026 contributor: fullname: Knudsen P. – volume: 144 start-page: 267 issue: 3 year: 1987 ident: CIT0011 publication-title: Nucl. Eng. Des. doi: 10.1016/0029-5493(87)90055-0 contributor: fullname: Nakajima T. – volume-title: IAEA-T1-TC-659. year: 1988 ident: CIT0013 contributor: fullname: Nakajima T. – ident: CIT0018 doi: 10.1016/0022-3115(83)90176-9 – volume-title: AERE-R9733 year: 1980 ident: CIT0020 contributor: fullname: Matzke H.J. – ident: CIT0027 – volume: 54 start-page: 58 year: 1987 ident: CIT0015 publication-title: Trans. Am. Nucl. Soc. contributor: fullname: Matsui T. – ident: CIT0023 – ident: CIT0004 – year: 1988 ident: CIT0014 publication-title: CRIEPI Rep. ET 88002 contributor: fullname: Kinoshita M. – volume: 2 start-page: 109 year: 1981 ident: CIT0006 publication-title: Res. Medianica contributor: fullname: Ito K. – year: 1985 ident: CIT0009 publication-title: JAERI-1298 contributor: fullname: Nakajima T. – volume-title: CRIEPI Rep. year: 1990 ident: CIT0028 contributor: fullname: Kameyama T. – ident: CIT0016 – volume: 56 start-page: 117 issue: 1 year: 1980 ident: CIT0017 publication-title: Nucl. Eng. Des. doi: 10.1016/0029-5493(80)90175-2 contributor: fullname: Ito K. – volume-title: Verification of the FEMAXI-m code, IAEA Specialists Mtg. on Water Reactor Fuel Element Performance Computer Modelling, Preston, UK year: 1982 ident: CIT0008 contributor: fullname: Okubo T. – volume: 56 start-page: 49 issue: 1 year: 1980 ident: CIT0002 publication-title: Nucl. Eng. Des. doi: 10.1016/0029-5493(80)90167-3 contributor: fullname: Kinoshita M. – ident: CIT0019 doi: 10.1016/0022-3115(73)90001-9 – ident: CIT0005 – ident: CIT0022 – volume-title: IAEA-TC ident: CIT0012 contributor: fullname: Nakajima T. – volume: 88 start-page: 69 year: 1985 ident: CIT0010 publication-title: Nucl. Eng. Des. doi: 10.1016/0029-5493(85)90046-9 contributor: fullname: Nakajima T. – volume: 149 year: 1980 ident: CIT0007 publication-title: IWGFPT/8 contributor: fullname: Ichikawa M. |
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Snippet | This paper is to cover brief history of the development of LWR fuel performance analysis codes in Japan. This includes the FEMAXI-III code which calculates... this paper is to cover brief history of the development of LWR fuel performance analysis codes in Japan. This includes the FEMAXI-III code which calculates... |
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SubjectTerms | Applied sciences computer codes Energy Exact sciences and technology finite element method fission gas release fuel cans fuel pellets fuel temperature fuel-cladding interactions Fuels light water reactors Nuclear fuels numerical solution performance analysis power ramp Preparation and processing of nuclear fuels reliability rim effect |
Title | Development of LWR Fuel Performance Analysis Codes |
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