Exploratory test of 288 °C radiation resistance of two USSR-produced reactor pressure vessel steels

J. R. Hawthorne; M. A. Sokolov; W. L. Server

doi:10.1520/stp12379s

Exploratory test of 288 °C radiation resistance of two USSR-produced reactor pressure vessel steels

J. R. Hawthorne, M. A. Sokolov, W. L. Server

Research output: Contribution to journal › Conference article › peer-review

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Abstract

Two USSR-produced forging steels representing the Cr-Mo-V forgings employed in the construction of USSR light-water VVER-440 reactor pressure vessels before and after 1980, respectively were investigated for irradiation effects on their Charpy V-notch ductilities. The materials differ primarily with their P content. The observed Charpy V-notch 41 J transition temperature elevation values are considerably less than the elevations predicted by NRC Regulatory Guide 1.99, Rev. 2. On the other hand, upper-shelf energy level reductions found for the pre-1980 material was higher.

Original language	English
Pages (from-to)	16-32
Number of pages	17
Journal	ASTM Special Technical Publication
Issue number	1366
DOIs	https://doi.org/10.1520/stp12379s
State	Published - 2000
Event	19th International Symposium: Effects of Radiation on Materials - Seattle, WA, USA Duration: Jun 16 1998 → Jun 18 1998

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@article{9ce3a40637cd4696beb9bd0ae899345c,

title = "Exploratory test of 288 °C radiation resistance of two USSR-produced reactor pressure vessel steels",

abstract = "Two USSR-produced forging steels representing the Cr-Mo-V forgings employed in the construction of USSR light-water VVER-440 reactor pressure vessels before and after 1980, respectively were investigated for irradiation effects on their Charpy V-notch ductilities. The materials differ primarily with their P content. The observed Charpy V-notch 41 J transition temperature elevation values are considerably less than the elevations predicted by NRC Regulatory Guide 1.99, Rev. 2. On the other hand, upper-shelf energy level reductions found for the pre-1980 material was higher.",

author = "Hawthorne, {J. R.} and Sokolov, {M. A.} and Server, {W. L.}",

year = "2000",

doi = "10.1520/stp12379s",

language = "English",

pages = "16--32",

journal = "ASTM Special Technical Publication",

issn = "1040-3094",

number = "1366",

note = "19th International Symposium: Effects of Radiation on Materials ; Conference date: 16-06-1998 Through 18-06-1998",

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T1 - Exploratory test of 288 °C radiation resistance of two USSR-produced reactor pressure vessel steels

AU - Hawthorne, J. R.

AU - Sokolov, M. A.

AU - Server, W. L.

PY - 2000

Y1 - 2000

N2 - Two USSR-produced forging steels representing the Cr-Mo-V forgings employed in the construction of USSR light-water VVER-440 reactor pressure vessels before and after 1980, respectively were investigated for irradiation effects on their Charpy V-notch ductilities. The materials differ primarily with their P content. The observed Charpy V-notch 41 J transition temperature elevation values are considerably less than the elevations predicted by NRC Regulatory Guide 1.99, Rev. 2. On the other hand, upper-shelf energy level reductions found for the pre-1980 material was higher.

AB - Two USSR-produced forging steels representing the Cr-Mo-V forgings employed in the construction of USSR light-water VVER-440 reactor pressure vessels before and after 1980, respectively were investigated for irradiation effects on their Charpy V-notch ductilities. The materials differ primarily with their P content. The observed Charpy V-notch 41 J transition temperature elevation values are considerably less than the elevations predicted by NRC Regulatory Guide 1.99, Rev. 2. On the other hand, upper-shelf energy level reductions found for the pre-1980 material was higher.

UR - http://www.scopus.com/inward/record.url?scp=0034482945&partnerID=8YFLogxK

U2 - 10.1520/stp12379s

DO - 10.1520/stp12379s

M3 - Conference article

AN - SCOPUS:0034482945

SN - 1040-3094

SP - 16

EP - 32

JO - ASTM Special Technical Publication

JF - ASTM Special Technical Publication

IS - 1366

T2 - 19th International Symposium: Effects of Radiation on Materials

Y2 - 16 June 1998 through 18 June 1998

ER -

Exploratory test of 288 °C radiation resistance of two USSR-produced reactor pressure vessel steels

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