Neutron-induced damage simulations: Beyond defect production cross-section, displacement per atom and iron-based metrics

Sublet, J.‐Ch.; Bondarenko, I. P.; Bonny, G.; Conlin, Jeremy Lloyd; Gilbert, Mark R.; Greenwood, Lawrence R.; Griffin, Patrick J.; Helgesson, Petter; Iwamoto, Yosuke; Khryachkov, V. A.; Khromyleva, Tatiana; Konobeyev, A.Yu.; Lazarev, N. P.; Lunéville, Laurence; Mota, F.; Ortiz, C.J.; Rochman, D.; Simakov, S.P.; Siméone, David; Sjöstrand, Henrik; Terentyev, D.; Vila, R.

doi:10.1140/epjp/i2019-12758-y

Cited by 21 publications

(1 citation statement)

References 154 publications

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“…In practice, this is a little used feature of transport simulations, which often does not go beyond, from a damage perspective, the simple dpa measure of damage dose. Alternatively, moving beyond dpa [409] can begin with evaluation tools such as SPECTRA-primary knock-on atom (PKA) [410,411], SPECTER [412] or dedicated event-generator codes such as PHITS [413,414], can calculate the distribution of recoil events, the so-called PKAs, which can be subsequently used in modelling to predict the creation and evolution of microstructural damage; for example, using the method of cluster dynamics [415]. In the case of alloys, including steels, codes such as DART [416] can even account for compound effects, where the total damage dose is not merely a linear combination of the evaluated damage in matrices of the individual elements making up a compound [417].…”

Section: Multiscale Modellingmentioning

confidence: 99%

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

et al. 2022

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Reduced activation ferritic-martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. Performance of these steels will deteriorate in-service due to neutron damage and transmutation-induced gases like helium/hydrogen at elevated operating temperatures. Here, after highlighting the operating conditions of fusion reactor concepts and a brief overview, the major irradiation-induced degradation challenges associated with RAFM/ODS steels are discussed. Their long-term degradation scenarios such as (i) low temperature hardening-embrittlement (LTHE) - including dose-temperature dependent yield stress, tensile elongations, necking ductility, test temperature effect on hardening, Charpy impact ductile to brittle transition temperature and fracture toughness, (ii) inter-mediate temperature cavity swelling, (iii) the effect of helium on LTHE and cavity swelling, (iv) irradiation creep and (v) tritium management issues are reviewed. The potential causes of LTHE are discussed that highlights need for advanced characterization techniques. Mechanical properties including tensile/Charpy impact of RAFM and ODS steels are compared to show that current generation of ODS steels also suffer from LTHE, and they can show irradiation hardening up to high temperatures, ~400-500 °C. To minimize this, future ODS steel development for FW/B specific application should target materials with lower Cr concentration (to minimize α’) and minimize other elements that could form embrittling phases under irradiation. RAFM steel designing activities targeting improvements in creep and LTHE are reviewed. The need to better understand synergistic effects of helium on thermo-mechanical properties in the entire temperature range of FW/B is highlighted. Because fusion operating conditions will be complex including stresses due to magnetic field, primary loads like coolant pressure, secondary loads from thermal gradients, and due to spatial variation in damage levels and gas production rates, an experimentally validated multi-scale modelling approach is suggested as a pathway to future reactor component designing such as for the fusion neutron science facility

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