Synergies between Fission and Fusion Nuclear Energy

Carré, Frank; Serpantie, J.P.

doi:10.1051/rgn/20071108

Cited by 1 publication

(2 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…exposed to cooler sodium at around 400 °C and the upper core structures to higher temperatures at around 550°C [3,6,7]. In both cases, lateral and axial neutronic protections limit radiation doses on these structures to less than a few dpa, while reactor core materials will be exposed to much higher doses.…”

Section: Materials and Service Conditionsmentioning

confidence: 99%

“…The choice of concepts to investigate for Gen IV has now, at least in France, been narrowed down from the initial 6 to the sodium cooled fast reactor as the main option and a higher temperature gas cooled fast reactor (GFR) as alternative [3]. Likewise, the concepts to be tested in ITER for the future fusion demonstration (DEMO) reactor, at least in Europe, have been reduced to two blanket modules with an upper temperature limit of 550 °C, with possible extension to 650°C [4].…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

High Temperature Creep-Fatigue Design and Service Experience

2008

View full text Add to dashboard Cite

Generation IV fission and future fusion reactors envisage development of more efficient high temperature concepts where materials performances under creep-fatigue hold the key to success. This paper presents extended experimental results obtained from creep, fatigue and creep-fatigue tests on the main structural materials retained for these concepts, namely: stainless steel type 316L(N), the conventional Modified 9Cr-1Mo martensitic steel and its low activation derivatives such as Eurofer steel, and their more advanced grades strengthened by oxide dispersion. It shows that the existing recommendations made in design codes adequately cover individual damage due to creep or fatigue but often fall short under combined creep-fatigue interaction. This is partly due to the difficulties of reproducing service conditions in laboratory. In this paper, results from tests performed on components removed from reactor, after long service, are used to refine code recommendations.Using the above combined assessment, it is concluded that there is good confidence in predicting creep-fatigue damage for austenitic stainless steels. For the martensitic steels the effects of cyclic softening and microstructure coarsening throughout the fatigue life need more consideration in creep-fatigue recommendation. In the long-term development of ferritic/martensitic oxide dispersion strengthened grades with stable microstructure and no cyclic softening, appears promising provided problems associated with their fabrication and embrittlement are resolved.

show abstract

Section: Materials and Service Conditionsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%