Tube sheet structural analysis of intermediate heat exchanger for fast breeder reactor 'Monju'
Creators
- 1. Hitachi Works, Hitachi Ltd. (Japan)
- 2. Mechanical Engineering Lab., Hitachi Ltd. (Japan)
- 3. Power Reactor and Nuclear Fuel Development Corp. (Japan)
Description
The Prototype Fast Breeder Reactor 'Monju' is the first power generating fast breeder reactor in Japan. We have been designing the components of the plant for manufacturing. Among these is the intermediate heat exchanger (IHX) which exchanges heat between primary and secondary sodium loop. The tube sheet of IHX (shell to ligament junction) is a difficult area from the view point of structural strength design under elevated temperature. To validate the structural integrity of tube sheet we performed the series of inelastic analysis and tube sheet thermal shock test using test pieces and half scale model of actual design. The results of inelastic analyses showed there is little progressive deformation around shell to ligament structural discontinuous junction. Furthermore, thermal shock tests showed no increase of an accumulative deformation. By these analyses and experiments, structural reliability of tube sheet could be shown. (author)
Files
33026525.pdf
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Additional details
Publishing Information
- Imprint Title
- International Atomic Energy Agency specialist meeting on advances in structural analysis for LMFBR applications. Summary report
- Imprint Pagination
- 334 p.
- Journal Page Range
- p. 218-232
- Report number
- IWGFR--44
Conference
- Title
- IAEA-IWGFR specialist meeting on advances in structural analysis for LMFBR applications
- Dates
- 11-15 Oct 1982
- Place
- Paris (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33026525
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEFORMATION; DESIGN; FABRICATION; HEAT EXCHANGERS; MECHANICAL STRUCTURES; MECHANICAL TESTS; MONJU REACTOR; PRIMARY COOLANT CIRCUITS; REACTOR COMPONENTS; SECONDARY COOLANT CIRCUITS; SODIUM; THERMAL SHOCK; THERMAL STRESSES
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS TESTING; METALS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SODIUM COOLED REACTORS; STRESSES; TESTING
Optional Information
- Notes
- 14 figs, 4 tabs
- Secondary number(s)
- CEA-N--2349