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 inJournal of nuclear science and technology Vol. 30; no. 1; pp. 1 - 17
Main Author KINOSHITA, Motoyasu
Format Journal Article
LanguageEnglish
Published Tokyo Taylor & Francis Group 01.01.1993
Atomic Energy Society of Japan
Taylor & Francis Ltd
Subjects
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
Asia
Japan
Performance evaluation
Finite element method
Nuclear fuel
Software
Clad
Light water reactor
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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.
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
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10.1016/0029-5493(87)90055-0
10.1016/0022-3115(83)90176-9
10.1016/0029-5493(80)90175-2
10.1016/0029-5493(80)90167-3
10.1016/0022-3115(73)90001-9
10.1016/0029-5493(85)90046-9
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Issue 1
Keywords Performance evaluation
Finite element method
Nuclear fuel
Software
Clad
Light water reactor
Language English
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Nakajima T. (CIT0012)
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Matzke H.J. (CIT0020) 1980
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Mogard H. (CIT0025) 1984
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Knudsen P. (CIT0026) 1989
CIT0005
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Kinoshita M. (CIT0014) 1988
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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
URI https://www.tandfonline.com/doi/abs/10.1080/18811248.1993.9734445
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Volume 30
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