A comparison of AISI type 316 and German type DIN 1.4970 stainless steel with regard to the first-wall lifetime
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Research context
OpenAlex topics: Fusion materials and technologies · Nuclear reactor physics and engineering · Microstructure and Mechanical Properties of Steels
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References (13)
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1. FWLTB — a mathematical model to calculate the lifetime of the fusion reactor first wall
2. FWLTB — a computer program for predicting the lifetime of a fusion reactor first wall
3. First wall life prediction by the FWLTB computer program
4. Results of strategic calculations for optimizing the first wall lifetime in a tokamak fusion reactor
5. Austenitic stainless steel bulk property considerations for fusion reactors
6. Structural evaluation of a tokamak reactor cylindrical module blanket concept
7. Empirical development of irradiation-induced swelling design equations10.13182/NT80-A32477 ↗
8. Temperature and fluence limits for a type 316 stainless-steel controlled thermonuclear reactor first wall10.13182/NT76-A31703 ↗
9. Mechanical properties of materials in fusion reactor first-wall and blanket systems
10. Neutron irradiation-induced embrittlement in type 316 and other austenitic steels and alloys10.1016/0022-3115(79)90034-5 ↗
11. Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environment
12. Creep-rupture properties of 20% cold-worked type 316 stainless steel after high fluence neutron irradiation10.13182/NT77-A31846 ↗
13. Latest results from the FWLTB computer code: The influence of swelling and irradiation creep on the stainless steel first wall of a fusion reactor