Radiation-induced precipitates in a self-ion irradiated cold-worked 316 austenitic stainless steel used for PWR baffle-bolts

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26620%2F18%3APU127370" target="_blank" >RIV/00216305:26620/18:PU127370 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1007/978-3-319-67244-1_36" target="_blank" >http://dx.doi.org/10.1007/978-3-319-67244-1_36</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1007/978-3-319-67244-1_36" target="_blank" >10.1007/978-3-319-67244-1_36</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Radiation-induced precipitates in a self-ion irradiated cold-worked 316 austenitic stainless steel used for PWR baffle-bolts

Popis výsledku v původním jazyce

5, meV Ni++, and Fe++, ion irradiations were performed to investigate radiation-induced precipitates evolution in a cold-worked 316 austenitic stainless steel at high doses and temperatures. The irradiation conditions were 23, dpa at 380, °C, 130, dpa at 380, °C, 23, dpa at 500, °C, and 15, dpa at 600, °C. TEM selected electron diffraction (SAED), TEM dark-field imaging and energy dispersive spectroscopy (EDS) mapping were used as complementary techniques to determine crystallography, morphology and chemical composition of radiation-induced precipitates. The precipitates were predominantly in form of the Ni–Si rich γ′ phase at all irradiation conditions. The EDS analysis further determined Ni–Si–Mo–P and Ni–Si–Mn rich precipitates after irradiation at 380 and 600, °C, respectively. The precipitates were found close to saturated state between 23 and 130, dpa at 380, °C irradiation conditions. A different effect of higher irradiation temperatures was found between 500 and 600, °C. In case of the irradiation to 23, dpa at 500, °C, the average size of precipitates was similar to irradiations at 380, °C, but the density was lower. However, the precipitates revealed large size and very low density following the irradiation to 15, dpa at 600, °C. The original dislocation network introduced by cold-working was found as dominant sink for intra-granular solute radiation-induced segregation (RIS) and possibly took place as primary nucleation site of radiation-induced precipitates at irradiation temperatures 380 and 500, °C. At the temperature 600, °C, the RIS at dislocation network almost vanished and the main nucleation sites became twin boundaries as more energetically favorable intra-granular sinks.

Název v anglickém jazyce

Radiation-induced precipitates in a self-ion irradiated cold-worked 316 austenitic stainless steel used for PWR baffle-bolts

Popis výsledku anglicky

5, meV Ni++, and Fe++, ion irradiations were performed to investigate radiation-induced precipitates evolution in a cold-worked 316 austenitic stainless steel at high doses and temperatures. The irradiation conditions were 23, dpa at 380, °C, 130, dpa at 380, °C, 23, dpa at 500, °C, and 15, dpa at 600, °C. TEM selected electron diffraction (SAED), TEM dark-field imaging and energy dispersive spectroscopy (EDS) mapping were used as complementary techniques to determine crystallography, morphology and chemical composition of radiation-induced precipitates. The precipitates were predominantly in form of the Ni–Si rich γ′ phase at all irradiation conditions. The EDS analysis further determined Ni–Si–Mo–P and Ni–Si–Mn rich precipitates after irradiation at 380 and 600, °C, respectively. The precipitates were found close to saturated state between 23 and 130, dpa at 380, °C irradiation conditions. A different effect of higher irradiation temperatures was found between 500 and 600, °C. In case of the irradiation to 23, dpa at 500, °C, the average size of precipitates was similar to irradiations at 380, °C, but the density was lower. However, the precipitates revealed large size and very low density following the irradiation to 15, dpa at 600, °C. The original dislocation network introduced by cold-working was found as dominant sink for intra-granular solute radiation-induced segregation (RIS) and possibly took place as primary nucleation site of radiation-induced precipitates at irradiation temperatures 380 and 500, °C. At the temperature 600, °C, the RIS at dislocation network almost vanished and the main nucleation sites became twin boundaries as more energetically favorable intra-granular sinks.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20501 - Materials engineering

Projekt

<a href="/cs/project/LM2015041" target="_blank" >LM2015041: CEITEC Nano</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2018

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

ISBN

978-3-319-67244-1

ISSN

—

e-ISSN

—

Počet stran výsledku

16

Strana od-do

565-580

Název nakladatele

Springer

Místo vydání

Neuveden

Místo konání akce

Portland

Datum konání akce

13. 8. 2017

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

—