Thermal and stress analyses with ANSYS program
Description
Some analyses of the heat conduction and elastic/inelastic stresses, carried out in Power Reactor and Nuclear Fuel Development Corporation (PNC) in fiscal 1973 using ANSYS (Engineering Analysis System) program, are summarized. In chapter I, the present state of structural analysis programs available for a FBR (fast breeder reactor) in PNC is explained. Chapter II is a brief description of the ANSYS current status. In chapter III are presented 8 examples of the steady-state and transient thermal analyses for fast-reactor plant components, and in chapter IV 5 examples of the inelastic structural analysis. With the advance in the field of finite element method, its applications in design study should extend progressively in the future. The present report, it is hoped, will contribute as references in similar analyses and at the same time help to understand the deformation and strain behaviors of structures. (Mori, K.)
Availability note (English)
MF available from INIS under the Report Number.
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Additional details
Additional titles
- Subtitle (English)
- ANSYS report 6-18
Publishing Information
- Imprint Pagination
- 418 p.
- Report number
- PNC-N--241-75-07
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 7244735
- Subject category
- S42: ENGINEERING; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- A CODES; CREEP; DEFORMATION; ELASTICITY; FAST REACTORS; FINITE ELEMENT METHOD; MECHANICAL STRUCTURES; NUMERICAL SOLUTION; PLANNING; PLASTICITY; STRAINS; STRESS ANALYSIS; THERMAL CONDUCTIVITY; THERMAL STRESSES; TRANSIENTS; TUBES
- Descriptors DEC
- COMPUTER CODES; EPITHERMAL REACTORS; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES; REACTORS; STRESSES; TENSILE PROPERTIES; THERMODYNAMIC PROPERTIES