Integrity of Safety-Related Fast Reactor Structures
Creators
- 1. Nuclear Power Co. (Risley) Ltd., Risley, Warrington, Lancs. (United Kingdom)
- 2. Springfields Nuclear Power Development Labs., United Kingdom Atomic Energy Authority, Springfields, Salwick, Preston, Lancs. (United Kingdom)
Description
The LMFBR contains several structural items whose integrity must be safeguarded during the life of the plant. These items include the main core support structures (strongback, diagrid) and the primary tank to which these structures are attached. In order to demonstrate an acceptable level of structural integrity, the chosen design philosophy must be supported by both analytical and experimental evidence. This paper describes the current approaches in the UK to these requirements. Section 2 describes the materials mechanical properties tests performed to date on both fracture toughness and fatigue crack growth in Type 316 austenitic stainless steel plate and weldments. This data illustrates the problems in identifying the relevant materials fracture parameters for use in assessments. Section 3 shows the test programmes in hand to extend the materials programmes to tests on structural features (mainly welded wide plate tests) which incorporate the complexity of weldments in a structural context. This includes experimental evidence on the effects of local weld residual stresses on structural failure. Various routes are open for the integrity assessment of FR structures. These are discussed in Section 4 but in effect they reduce to a fracture mechanics approach using some technique to cope with elastic-plastic fracture. The main problems at present relate to our ability in analysis to cope with residual stresses and the post-initiation region of the fracture resistance curve. Also, there is the problem of initial defect sizing by current NDE techniques. Current conservative analytical assessments give acceptable defect sizes of order a few millimetres in irradiated weldments. Finally, Section 5 discusses the options open in design to cope with safety related structures under normal and abnormal loading conditions. It is clear that several options exist in design to satisfy the demand for high integrity
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45086162.pdf
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Additional details
Publishing Information
- Imprint Title
- Specialists#Right Single Quotation Mark# Meeting on Demonstration of Structural Integrity under Normal and Faulted Conditions. Summary Report
- Imprint Pagination
- 62 p.
- Journal Page Range
- p. 21-45
- Report number
- IWGFR--36
Conference
- Title
- IAEA-IWGFR Specialists' Meeting on Demonstration of Structural Integrity under Normal and Faulted Conditions
- Dates
- 3-5 Jun 1980
- Place
- Chester (United Kingdom)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45086162
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUSTENITIC STEELS; CRACK PROPAGATION; DEFECTS; FATIGUE; FRACTURE MECHANICS; FRACTURE PROPERTIES; FRACTURES; IRRADIATION; LMFBR TYPE REACTORS; RESIDUAL STRESSES; SAFEGUARDS; SAFETY
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; MECHANICS; REACTORS; STEELS; STRESSES; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 9 refs., tabs., figs.