Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld

S. K. Iskander; R. K. Nanstad; C. A. Baldwin; D. W. Heatherly; M. K. Miller; I. Remec

doi:10.1520/STP10540S

Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld

S. K. Iskander, R. K. Nanstad, C. A. Baldwin, D. W. Heatherly, M. K. Miller, I. Remec

STS Project Technical Systems

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The Charpy impact response of reirradiated Heavy-Section Steel Irradiation (HSSI) Program Weld 73W has been determined at three fluence levels. The Charpy specimens had previously been irradiated at 288°C to 1.8 x 10¹⁹ cm"² (E > 1 MeV) and annealed at 454°C for 168 h. The results show that the change in the 41-J Charpy energy level transition temperature (ATT^., ) of the reirradiated specimens is slightly higher than predicted by the vertical shift method, but significantly less than predicted by the lateral shift method. Previous results have also shown that the upper-shelf energy (USE) over-recovers as a consequence of annealing, which may explain why the USE value after a significant amount of reirradiation is approximately equal to the USE value in the unirradiated condition.

Original language	English
Title of host publication	Effects of Radiation on Materials
Subtitle of host publication	20th International Symposium
Editors	Stan T. Rosinski, Martin L. Grossbeck, Todd R. Allen, Arvind S. Kumar
Publisher	ASTM International
Pages	302-314
Number of pages	13
ISBN (Electronic)	9780803128781
DOIs	https://doi.org/10.1520/STP10540S
State	Published - 2001
Event	20th International Symposium on Effects of Radiation on Materials 2000 - Williamsburg, United States Duration: Jun 6 2000 → Jun 8 2000

Publication series

Name	ASTM Special Technical Publication
Volume	STP 1405
ISSN (Print)	0066-0558

Conference

Conference	20th International Symposium on Effects of Radiation on Materials 2000
Country/Territory	United States
City	Williamsburg
Period	06/6/00 → 06/8/00

Funding

This research is sponsored by the Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, under Interagency Agreement DOE 1886-N695-3W with the U.S. Department of Energy under Contract DE-AC05-00OR22725 with UT-Battelle, LLC. It was performed in the Heavy-Section Steel Irradiation Program, managed by T. M. Rosseel. The authors appreciate the financial support from the U.S. Nuclear Regulatory Commission. The authors also appreciate the technical review by J. G. Merkle, manuscript preparation by J. L. Bishop, and many helpful suggestions from M. A. Sokolov and the efforts of the hot cell staff: L. J. Turner, P. S. Bishop, G. W. Parks, and the Charpy testing by R. L. Swain. The authors also acknowledge P. Pareige for measurements of the matrix copper compositions in the PWHT, I, and IA conditions shown in Table 3.

Keywords

Charpy V-notch
annealing
copper
irradiation
neutron
reactor pressure vessel
weld metal

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10.1520/STP10540S

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Iskander, S. K., Nanstad, R. K., Baldwin, C. A., Heatherly, D. W., Miller, M. K., & Remec, I. (2001). Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld. In S. T. Rosinski, M. L. Grossbeck, T. R. Allen, & A. S. Kumar (Eds.), Effects of Radiation on Materials: 20th International Symposium (pp. 302-314). (ASTM Special Technical Publication; Vol. STP 1405). ASTM International. https://doi.org/10.1520/STP10540S

@inproceedings{1d9488c39bba4d068efe4965d1c179c6,

title = "Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld",

abstract = "The Charpy impact response of reirradiated Heavy-Section Steel Irradiation (HSSI) Program Weld 73W has been determined at three fluence levels. The Charpy specimens had previously been irradiated at 288°C to 1.8 x 1019 cm{"}2 (E > 1 MeV) and annealed at 454°C for 168 h. The results show that the change in the 41-J Charpy energy level transition temperature (ATT\textasciicircum{}., ) of the reirradiated specimens is slightly higher than predicted by the vertical shift method, but significantly less than predicted by the lateral shift method. Previous results have also shown that the upper-shelf energy (USE) over-recovers as a consequence of annealing, which may explain why the USE value after a significant amount of reirradiation is approximately equal to the USE value in the unirradiated condition.",

keywords = "Charpy V-notch, annealing, copper, irradiation, neutron, reactor pressure vessel, weld metal",

author = "Iskander, \{S. K.\} and Nanstad, \{R. K.\} and Baldwin, \{C. A.\} and Heatherly, \{D. W.\} and Miller, \{M. K.\} and I. Remec",

note = "Publisher Copyright: {\textcopyright} 2001 by ASTM International.; 20th International Symposium on Effects of Radiation on Materials 2000 ; Conference date: 06-06-2000 Through 08-06-2000",

year = "2001",

doi = "10.1520/STP10540S",

language = "English",

series = "ASTM Special Technical Publication",

publisher = "ASTM International",

pages = "302--314",

editor = "Rosinski, \{Stan T.\} and Grossbeck, \{Martin L.\} and Allen, \{Todd R.\} and Kumar, \{Arvind S.\}",

booktitle = "Effects of Radiation on Materials",

}

Iskander, SK, Nanstad, RK, Baldwin, CA, Heatherly, DW, Miller, MK & Remec, I 2001, Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld. in ST Rosinski, ML Grossbeck, TR Allen & AS Kumar (eds), Effects of Radiation on Materials: 20th International Symposium. ASTM Special Technical Publication, vol. STP 1405, ASTM International, pp. 302-314, 20th International Symposium on Effects of Radiation on Materials 2000, Williamsburg, United States, 06/6/00. https://doi.org/10.1520/STP10540S

Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld. / Iskander, S. K.; Nanstad, R. K.; Baldwin, C. A. et al.
Effects of Radiation on Materials: 20th International Symposium. ed. / Stan T. Rosinski; Martin L. Grossbeck; Todd R. Allen; Arvind S. Kumar. ASTM International, 2001. p. 302-314 (ASTM Special Technical Publication; Vol. STP 1405).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld

AU - Iskander, S. K.

AU - Nanstad, R. K.

AU - Baldwin, C. A.

AU - Heatherly, D. W.

AU - Miller, M. K.

AU - Remec, I.

PY - 2001

Y1 - 2001

N2 - The Charpy impact response of reirradiated Heavy-Section Steel Irradiation (HSSI) Program Weld 73W has been determined at three fluence levels. The Charpy specimens had previously been irradiated at 288°C to 1.8 x 1019 cm"2 (E > 1 MeV) and annealed at 454°C for 168 h. The results show that the change in the 41-J Charpy energy level transition temperature (ATT^., ) of the reirradiated specimens is slightly higher than predicted by the vertical shift method, but significantly less than predicted by the lateral shift method. Previous results have also shown that the upper-shelf energy (USE) over-recovers as a consequence of annealing, which may explain why the USE value after a significant amount of reirradiation is approximately equal to the USE value in the unirradiated condition.

AB - The Charpy impact response of reirradiated Heavy-Section Steel Irradiation (HSSI) Program Weld 73W has been determined at three fluence levels. The Charpy specimens had previously been irradiated at 288°C to 1.8 x 1019 cm"2 (E > 1 MeV) and annealed at 454°C for 168 h. The results show that the change in the 41-J Charpy energy level transition temperature (ATT^., ) of the reirradiated specimens is slightly higher than predicted by the vertical shift method, but significantly less than predicted by the lateral shift method. Previous results have also shown that the upper-shelf energy (USE) over-recovers as a consequence of annealing, which may explain why the USE value after a significant amount of reirradiation is approximately equal to the USE value in the unirradiated condition.

KW - Charpy V-notch

KW - annealing

KW - copper

KW - irradiation

KW - neutron

KW - reactor pressure vessel

KW - weld metal

UR - https://www.scopus.com/pages/publications/85164953967

U2 - 10.1520/STP10540S

DO - 10.1520/STP10540S

M3 - Conference contribution

AN - SCOPUS:85164953967

T3 - ASTM Special Technical Publication

SP - 302

EP - 314

BT - Effects of Radiation on Materials

A2 - Rosinski, Stan T.

A2 - Grossbeck, Martin L.

A2 - Allen, Todd R.

A2 - Kumar, Arvind S.

PB - ASTM International

T2 - 20th International Symposium on Effects of Radiation on Materials 2000

Y2 - 6 June 2000 through 8 June 2000

ER -

Reirradiation Response Rate of a High-Copper Reactor Pressure Vessel Weld

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