PFR fuel cladding transient test results and analysis
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Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear and radioactivity studies
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References (13)
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1. D.R. Duncan and C.W. Hunter, Post-irradiation cladding strength under biaxial loading with an increasing temperature ramp, ASTM STP 725, pp. 443–451.10.1520/STP28228S ↗
2. Kear · Harwell Res. Rep. AERE.R10907 · 1983
3. Mechanical properties of unirradiated fast reactor cladding during simulated overpower transients
4. Controlled biaxial strain-rate testing of 20% cold worked type 316 stainless steel fast reactor cladding10.13182/NT83-A33302 ↗
5. Effects of irradiation temperature, fluence and heating rate on post-irradiation flow properties of cladding under simulated temperature transient heating and deformation conditions
6. Mechanical properties of fast reactor fuel cladding for transient analysis
7. Mechanical properties of transient-tested irradiated fast reactor cladding
8. Fuel Adjacency Effects on Fast Reactor Cladding Mechanical Properties
9. Beere · Res. Mechanica · 1981 · 2 · 189
10. The origin and consequences of radial helium profiles in fast cladding10.13182/NT82-A32932 ↗
11. Liquid-metal embrittlement of AISI 316 stainless steel by Te—Cs mixture
12. Evidence for liquid—metal embrittlement of 20% cold worked Type 316 by cesium—tellurium fission products
13. Compilation of fission product yields velocities nuclear center — 1974