Theoretical analysis of fuel vibration in fast burst reactors
Creators
- 1. Tokyo Univ. (Japan). Nuclear Engineering Research Lab.
Description
The fuel of a fast burst reactor is subject to vibrations occasioned by rapid temperature rise when the reactivity in the core is suddenly increased. This paper covers an analysis of such fuel vibration in the fast neutron source reactor ''YAYOI'' under pulsed operation, with use made of the finite element method, and adopting as parameters the rate of temperature rise and the spatial temperature distribution. An analytical solution is also obtained assuming that the fuel is under plane stress, for comparison with the results derived by the finite element method. Agreement between the two results is very good within the bounds of the plane stress condition. The results indicate that the amplitudes of dynamic displacement and stress increase with rising rate of energy release. The relation between these quantities is presented. (auth.)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.17.365Additional details
Additional titles
- Original title (Japanese)
- 高速パルス炉における燃料要素の振動現象に関する解析
Identifiers
- DOI
- 10.3327/jaesj.17.365;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 17
- Journal Issue
- 7
- Journal Page Range
- p. 365-375
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53100726
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANALYTICAL SOLUTION; FINITE ELEMENT METHOD; FUEL CANS; FUEL ELEMENTS; HEATING; MECHANICAL VIBRATIONS; PULSED IRRADIATION; PULSED REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION; STRAINS; STRESS ANALYSIS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; THERMAL STRESSES; YAYOI REACTOR
- Descriptors DEC
- CALCULATION METHODS; DISTRIBUTION; EPITHERMAL REACTORS; FAST REACTORS; IRRADIATION; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STRESSES; TEMPERATURE RANGE
Optional Information
- Notes
- 6269300; This record replaces 07273550