Investigation of Pb-Li compatibility issues for the dual coolant blanket concept

B. A. Pint; J. L. Moser; P. F. Tortorelli

doi:10.1016/j.jnucmat.2007.03.206

Investigation of Pb-Li compatibility issues for the dual coolant blanket concept

B. A. Pint, J. L. Moser, P. F. Tortorelli

Materials Science and Technology Div

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

54 Scopus citations

Abstract

One proposed blanket concept uses advanced ferritic alloys and a SiC/SiC composite flow channel insert with both Pb-17 at.%Li and He coolants. As the first step in determining the long-term compatibility of SiC/SiC in Pb-Li, specimens of high-purity, chemical vapor deposited (CVD) SiC were exposed in capsules for up to 5000 h at 800 °C and 1000 h at 1200 °C. Dissolved Si was detected in the Pb-Li after the highest temperature exposures suggesting that SiC may be limited to <1100 °C in Pb-Li. Aluminide coatings are being considered for corrosion resistant coatings for the tubing between the first wall and the heat exchanger. Initial results indicate that, in Pb-Li at 700 °C, FeCrAl, Fe₃Al and NiAl form a protective alumina layer which reduces dissolution compared to type 316 stainless steel.

Original language	English
Pages (from-to)	1150-1154
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	367-370 B
Issue number	SPEC. ISS.
DOIs	https://doi.org/10.1016/j.jnucmat.2007.03.206
State	Published - Aug 1 2007

Funding

The research was sponsored by the US Department of Energy (DOE), Office of Fusion Energy Sciences, Fusion Energy Materials Program, under contract DE-AC05-00OR22725 with UT-Battelle, LLC. D.F. Wilson and J.R. DiStefano consulted on the experimental procedure. H. Longmire and L. Walker assisted with the experimental work. S.J. Pawel, J.R. DiStefano and S.J. Zinkle provided comments on the manuscript.

Funders	Funder number
Fusion Energy Materials Program	DE-AC05-00OR22725
U.S. Department of Energy
Fusion Energy Sciences

Access to Document

10.1016/j.jnucmat.2007.03.206

Cite this

@article{04f18c6d0e254c7884e4d23bd94bbb9c,

title = "Investigation of Pb-Li compatibility issues for the dual coolant blanket concept",

abstract = "One proposed blanket concept uses advanced ferritic alloys and a SiC/SiC composite flow channel insert with both Pb-17 at.%Li and He coolants. As the first step in determining the long-term compatibility of SiC/SiC in Pb-Li, specimens of high-purity, chemical vapor deposited (CVD) SiC were exposed in capsules for up to 5000 h at 800 °C and 1000 h at 1200 °C. Dissolved Si was detected in the Pb-Li after the highest temperature exposures suggesting that SiC may be limited to <1100 °C in Pb-Li. Aluminide coatings are being considered for corrosion resistant coatings for the tubing between the first wall and the heat exchanger. Initial results indicate that, in Pb-Li at 700 °C, FeCrAl, Fe3Al and NiAl form a protective alumina layer which reduces dissolution compared to type 316 stainless steel.",

author = "Pint, {B. A.} and Moser, {J. L.} and Tortorelli, {P. F.}",

year = "2007",

month = aug,

day = "1",

doi = "10.1016/j.jnucmat.2007.03.206",

language = "English",

volume = "367-370 B",

pages = "1150--1154",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

number = "SPEC. ISS.",

}

TY - JOUR

T1 - Investigation of Pb-Li compatibility issues for the dual coolant blanket concept

AU - Pint, B. A.

AU - Moser, J. L.

AU - Tortorelli, P. F.

PY - 2007/8/1

Y1 - 2007/8/1

N2 - One proposed blanket concept uses advanced ferritic alloys and a SiC/SiC composite flow channel insert with both Pb-17 at.%Li and He coolants. As the first step in determining the long-term compatibility of SiC/SiC in Pb-Li, specimens of high-purity, chemical vapor deposited (CVD) SiC were exposed in capsules for up to 5000 h at 800 °C and 1000 h at 1200 °C. Dissolved Si was detected in the Pb-Li after the highest temperature exposures suggesting that SiC may be limited to <1100 °C in Pb-Li. Aluminide coatings are being considered for corrosion resistant coatings for the tubing between the first wall and the heat exchanger. Initial results indicate that, in Pb-Li at 700 °C, FeCrAl, Fe3Al and NiAl form a protective alumina layer which reduces dissolution compared to type 316 stainless steel.

AB - One proposed blanket concept uses advanced ferritic alloys and a SiC/SiC composite flow channel insert with both Pb-17 at.%Li and He coolants. As the first step in determining the long-term compatibility of SiC/SiC in Pb-Li, specimens of high-purity, chemical vapor deposited (CVD) SiC were exposed in capsules for up to 5000 h at 800 °C and 1000 h at 1200 °C. Dissolved Si was detected in the Pb-Li after the highest temperature exposures suggesting that SiC may be limited to <1100 °C in Pb-Li. Aluminide coatings are being considered for corrosion resistant coatings for the tubing between the first wall and the heat exchanger. Initial results indicate that, in Pb-Li at 700 °C, FeCrAl, Fe3Al and NiAl form a protective alumina layer which reduces dissolution compared to type 316 stainless steel.

UR - http://www.scopus.com/inward/record.url?scp=34447525274&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2007.03.206

DO - 10.1016/j.jnucmat.2007.03.206

M3 - Article

AN - SCOPUS:34447525274

SN - 0022-3115

VL - 367-370 B

SP - 1150

EP - 1154

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - SPEC. ISS.

ER -

Investigation of Pb-Li compatibility issues for the dual coolant blanket concept

Abstract

Funding

Access to Document

Other files and links

Fingerprint

Cite this