Design of High Temperature Reactor Vessel Using ANSYS Software
Description
Design calculation and evaluation of material strength for high temperature reactor vessel based on the design of HTR-10 high temperature reactor vessel were carried out by using the ANSYS 5.4 software. ANSYS software was applied to calculate the combined load from thermal and pressure load. Evaluation of material strength was performed by calculate and determine the distribution of temperature, stress and strain in the thickness direction of vessel, and compared with its material strength for designed. The calculation was based on the inner wall temperature of vessel of 600oC and the outer temperature of 500 and 600oC. Result of calculation gave the maximum stress for outer temperature of 600oC was 288 N/ mm2 and strain of 0.000187. For outer temperature of 500oC the maximum stress was 576 N/ mm2 and strain of 0.003. Based on the analysis result, the material of steel SA 516-70 with limited stress for design of 308 N/ mm2 can be used for vessel material with outer wall temperature of 600oC
Files
37088862.pdf
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Additional details
Additional titles
- Original title (Indonesian)
- Desain Tangki Reaktor Temperatur Tinggi Menggunakan Software ANSYS
Publishing Information
- Publisher
- Centre for Development of Advanced Reactor System, National Atomic Energy Agency
- Imprint Place
- Serpong (Indonesia)
- Imprint Title
- Proceedings of the 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities
- Imprint Pagination
- 375 p.
- Journal Page Range
- p. 313-324
- ISSN
- 0854-2910
- Report number
- INIS-ID--033
Conference
- Title
- 9. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities
- Original Conference Title
- Seminar Nasional ke-9 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir
- Dates
- 20 Aug 2003
- Place
- Jakarta (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 37088862
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; COMPUTER CODES; DESIGN; FINITE ELEMENT METHOD; HTR REACTOR; REACTOR VESSELS; STRAINS; STRESSES; TEMPERATURE RANGE; YIELD STRENGTH
- Descriptors DEC
- CALCULATION METHODS; CONTAINERS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8refs; tabs; 4figs Imprint:Prosiding Seminar Nasional ke-9 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir