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

Result code in 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>

Result on the web

<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>

Result language

angličtina

Original language name

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

Original language description

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.

Czech name

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Czech description

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Type

D - Article in proceedings

CEP classification

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OECD FORD branch

20501 - Materials engineering

Project

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

Continuities

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

Publication year

2018

Confidentiality

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

Article name in the collection

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

ISBN

978-3-319-67244-1

ISSN

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e-ISSN

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Number of pages

16

Pages from-to

565-580

Publisher name

Springer

Place of publication

Neuveden

Event location

Portland

Event date

Aug 13, 2017

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

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