ITER structural design criteria and their extension to advanced reactor blankets
Source abstract
Abstract
Applications of the recent ITER structural design criteria (ISDC) are illustrated by two components. First, the low-temperature-design rules are applied to copper alloys that are particularly prone to irradiation embrittlement at relatively low fluences at certain temperatures. Allowable stresses are derived and the impact of the embrittlement on allowable surface heat flux of a simple first-wall/limiter design is demonstrated. Next, the high-temperature-design rules of ISDC are applied to evaporation of lithium and vapor extraction (EVOLVE), a blanket design concept currently being investigated under the US Advanced Power Extraction (APEX) program. A single tungsten first-wall tube is considered for thermal and stress analyses by finite-element method.
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Research context
OpenAlex topics: Fusion materials and technologies · Superconducting Materials and Applications · Nuclear reactor physics and engineering
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References (6)
Show source-provided references
1. ITER structural design criteria for in-vessel components (ISDC), ITER IDoMS S74MA1 97-12-12 R0.2, Appendix A IDoMS G74MA2 98-06-26 F1, 1998
2. S. Majumdar, P. Smith, in: Proceedings of the Fourth International Symposium on Fusion Nuclear Technology (ISFNT-4), Tokyo, 6–11 April 1997
3. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsections NB and NH, Edition July, 1995
4. RCC-MR Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, Section I, Subsection B: Class 1 components, Edition 1985
5. R.F. Mattas et al., in: Presented at the Fifth International Symposium on Fusion Nuclear Technology (ISFNT-5) in Rome, 19–24 September 1999
6. S. Majumdar, in: Presented at the Fifth International Symposium on Fusion Nuclear Technology (ISFNT-5) in Rome, 19–24 September 1999