Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

N. Dianne Bull Ezell; Stephen S. Raiman; J. Matt Kurley; Joel McDuffee

doi:10.1016/j.net.2020.07.042

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

N. Dianne Bull Ezell
, Stephen S. Raiman
, J. Matt Kurley
, Joel McDuffee

Research output: Contribution to journal › Article › peer-review

21 Scopus citations

Abstract

Capsules containing NaCl–MgCl₂ salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation–corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts. Index Terms: Molten salt reactor, Corrosion, Irradiation, High-temperature experiment.

Original language	English
Pages (from-to)	920-926
Number of pages	7
Journal	Nuclear Engineering and Technology
Volume	53
Issue number	3
DOIs	https://doi.org/10.1016/j.net.2020.07.042
State	Published - Mar 2021
Externally published	Yes

Keywords

Corrosion
High-temperature experiment
Irradiation
Molten Salt Reactor

Access to Document

10.1016/j.net.2020.07.042

Cite this

@article{ac0da27611ac4445a6e69fcafd3826e5,

title = "Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt",

abstract = "Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation–corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts. Index Terms: Molten salt reactor, Corrosion, Irradiation, High-temperature experiment.",

keywords = "Corrosion, High-temperature experiment, Irradiation, Molten Salt Reactor",

author = "Ezell, \{N. Dianne Bull\} and Raiman, \{Stephen S.\} and Kurley, \{J. Matt\} and Joel McDuffee",

note = "Publisher Copyright: {\textcopyright} 2020 Korean Nuclear Society",

year = "2021",

month = mar,

doi = "10.1016/j.net.2020.07.042",

language = "English",

volume = "53",

pages = "920--926",

journal = "Nuclear Engineering and Technology",

issn = "1738-5733",

publisher = "Korean Nuclear Society",

number = "3",

}

TY - JOUR

T1 - Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

AU - Ezell, N. Dianne Bull

AU - Raiman, Stephen S.

AU - Kurley, J. Matt

AU - McDuffee, Joel

PY - 2021/3

Y1 - 2021/3

N2 - Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation–corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts. Index Terms: Molten salt reactor, Corrosion, Irradiation, High-temperature experiment.

AB - Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation–corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts. Index Terms: Molten salt reactor, Corrosion, Irradiation, High-temperature experiment.

KW - Corrosion

KW - High-temperature experiment

KW - Irradiation

KW - Molten Salt Reactor

UR - https://www.scopus.com/pages/publications/85089979267

U2 - 10.1016/j.net.2020.07.042

DO - 10.1016/j.net.2020.07.042

M3 - Article

AN - SCOPUS:85089979267

SN - 1738-5733

VL - 53

SP - 920

EP - 926

JO - Nuclear Engineering and Technology

JF - Nuclear Engineering and Technology

IS - 3

ER -

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt

Abstract

Keywords

Access to Document

Other files and links

Fingerprint

Cite this