Analysis of First Pressure Vessel Surveillance Capsule from Krško Nuclear Power Plant

I. Kodeli; I. Remec; B. Glumac; M. Najžer; A. Loose

doi:10.1520/STP10067S

Analysis of First Pressure Vessel Surveillance Capsule from Krško Nuclear Power Plant

I. Kodeli, I. Remec, B. Glumac, M. Najžer, A. Loose

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

Abstract

Results of the analysis of the first pressure vessel (PV) radiation embrittlement surveillance capsule from Krško nuclear power plant are presented. The capsule was removed and tested after 1.75 effective full power years of operation. Neutron flux and spectrum were calculated with DOT 3.5 and 4.2 transport codes at the locations of the specimens in the capsule and in the pressure vessel. Nickel, iron, copper, cobalt, Np-237, and U-238 neutron dosimeters were irradiated in surveillance capsules. Experimentally determined reaction rates were compared to values calculated from the neutron transport calculation,with source strength corresponding to the nominal reactor thermal power. Good agreement (within 15%) was found for threshold neutron detectors. The STAY'SL unfolding code was used to adjust the measured and calculated reaction rates and neutron fluences. Shifts in the RTNdt temperature determined from Charpy V-notch curves for irradiated material relative to that of unirradiated materials were compared with shifts predicted by NRC Regulatory Guide 1.99, Rev. 1 and Rev. 2, at the neutron exposure of 7 to 9 E18 n∙cm⁻² (ϕ(E > 1 MeV)) experienced by specimens taking into account the chemical composition of PV steel.

Original language	English
Title of host publication	Reactor Dosimetry
Subtitle of host publication	Methods, Applications, and Standardization
Editors	Harry Farrar, Ezra Parvin Lippincott
Publisher	ASTM International
Pages	115-120
Number of pages	6
ISBN (Electronic)	9780803111844
DOIs	https://doi.org/10.1520/STP10067S
State	Published - 1989
Externally published	Yes
Event	6th ASTM-Euratom Symposium on Reactor Dosimetry: Methods, Applications, and Standardization - Jackson Hole, United States Duration: May 31 1987 → Jun 5 1987

Publication series

Name	ASTM Special Technical Publication
Volume	STP 1001
ISSN (Print)	0066-0558

Conference

Conference	6th ASTM-Euratom Symposium on Reactor Dosimetry: Methods, Applications, and Standardization
Country/Territory	United States
City	Jackson Hole
Period	05/31/87 → 06/5/87

Keywords

RTNDT shifts
light water reactor
neutron dosimetry
pressure vessel surveillance

Access to Document

10.1520/STP10067S

Cite this

Kodeli, I., Remec, I., Glumac, B., Najžer, M., & Loose, A. (1989). Analysis of First Pressure Vessel Surveillance Capsule from Krško Nuclear Power Plant. In H. Farrar, & E. P. Lippincott (Eds.), Reactor Dosimetry: Methods, Applications, and Standardization (pp. 115-120). (ASTM Special Technical Publication; Vol. STP 1001). ASTM International. https://doi.org/10.1520/STP10067S

@inproceedings{142f9da1d0c54646b66b58b875b2beb5,

title = "Analysis of First Pressure Vessel Surveillance Capsule from Kr{\v s}ko Nuclear Power Plant",

abstract = "Results of the analysis of the first pressure vessel (PV) radiation embrittlement surveillance capsule from Kr{\v s}ko nuclear power plant are presented. The capsule was removed and tested after 1.75 effective full power years of operation. Neutron flux and spectrum were calculated with DOT 3.5 and 4.2 transport codes at the locations of the specimens in the capsule and in the pressure vessel. Nickel, iron, copper, cobalt, Np-237, and U-238 neutron dosimeters were irradiated in surveillance capsules. Experimentally determined reaction rates were compared to values calculated from the neutron transport calculation,with source strength corresponding to the nominal reactor thermal power. Good agreement (within 15%) was found for threshold neutron detectors. The STAY'SL unfolding code was used to adjust the measured and calculated reaction rates and neutron fluences. Shifts in the RTNdt temperature determined from Charpy V-notch curves for irradiated material relative to that of unirradiated materials were compared with shifts predicted by NRC Regulatory Guide 1.99, Rev. 1 and Rev. 2, at the neutron exposure of 7 to 9 E18 n∙cm−2 (ϕ(E > 1 MeV)) experienced by specimens taking into account the chemical composition of PV steel.",

keywords = "RTNDT shifts, light water reactor, neutron dosimetry, pressure vessel surveillance",

author = "I. Kodeli and I. Remec and B. Glumac and M. Naj{\v z}er and A. Loose",

note = "Publisher Copyright: Copyright {\textcopyright} 1989 by ASTM International.; 6th ASTM-Euratom Symposium on Reactor Dosimetry: Methods, Applications, and Standardization ; Conference date: 31-05-1987 Through 05-06-1987",

year = "1989",

doi = "10.1520/STP10067S",

language = "English",

series = "ASTM Special Technical Publication",

publisher = "ASTM International",

pages = "115--120",

editor = "Harry Farrar and Lippincott, {Ezra Parvin}",

booktitle = "Reactor Dosimetry",

}

Kodeli, I, Remec, I, Glumac, B, Najžer, M & Loose, A 1989, Analysis of First Pressure Vessel Surveillance Capsule from Krško Nuclear Power Plant. in H Farrar & EP Lippincott (eds), Reactor Dosimetry: Methods, Applications, and Standardization. ASTM Special Technical Publication, vol. STP 1001, ASTM International, pp. 115-120, 6th ASTM-Euratom Symposium on Reactor Dosimetry: Methods, Applications, and Standardization, Jackson Hole, United States, 05/31/87. https://doi.org/10.1520/STP10067S

Analysis of First Pressure Vessel Surveillance Capsule from Krško Nuclear Power Plant. / Kodeli, I.; Remec, I.; Glumac, B. et al.
Reactor Dosimetry: Methods, Applications, and Standardization. ed. / Harry Farrar; Ezra Parvin Lippincott. ASTM International, 1989. p. 115-120 (ASTM Special Technical Publication; Vol. STP 1001).

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

TY - GEN

T1 - Analysis of First Pressure Vessel Surveillance Capsule from Krško Nuclear Power Plant

AU - Kodeli, I.

AU - Remec, I.

AU - Glumac, B.

AU - Najžer, M.

AU - Loose, A.

PY - 1989

Y1 - 1989

N2 - Results of the analysis of the first pressure vessel (PV) radiation embrittlement surveillance capsule from Krško nuclear power plant are presented. The capsule was removed and tested after 1.75 effective full power years of operation. Neutron flux and spectrum were calculated with DOT 3.5 and 4.2 transport codes at the locations of the specimens in the capsule and in the pressure vessel. Nickel, iron, copper, cobalt, Np-237, and U-238 neutron dosimeters were irradiated in surveillance capsules. Experimentally determined reaction rates were compared to values calculated from the neutron transport calculation,with source strength corresponding to the nominal reactor thermal power. Good agreement (within 15%) was found for threshold neutron detectors. The STAY'SL unfolding code was used to adjust the measured and calculated reaction rates and neutron fluences. Shifts in the RTNdt temperature determined from Charpy V-notch curves for irradiated material relative to that of unirradiated materials were compared with shifts predicted by NRC Regulatory Guide 1.99, Rev. 1 and Rev. 2, at the neutron exposure of 7 to 9 E18 n∙cm−2 (ϕ(E > 1 MeV)) experienced by specimens taking into account the chemical composition of PV steel.

AB - Results of the analysis of the first pressure vessel (PV) radiation embrittlement surveillance capsule from Krško nuclear power plant are presented. The capsule was removed and tested after 1.75 effective full power years of operation. Neutron flux and spectrum were calculated with DOT 3.5 and 4.2 transport codes at the locations of the specimens in the capsule and in the pressure vessel. Nickel, iron, copper, cobalt, Np-237, and U-238 neutron dosimeters were irradiated in surveillance capsules. Experimentally determined reaction rates were compared to values calculated from the neutron transport calculation,with source strength corresponding to the nominal reactor thermal power. Good agreement (within 15%) was found for threshold neutron detectors. The STAY'SL unfolding code was used to adjust the measured and calculated reaction rates and neutron fluences. Shifts in the RTNdt temperature determined from Charpy V-notch curves for irradiated material relative to that of unirradiated materials were compared with shifts predicted by NRC Regulatory Guide 1.99, Rev. 1 and Rev. 2, at the neutron exposure of 7 to 9 E18 n∙cm−2 (ϕ(E > 1 MeV)) experienced by specimens taking into account the chemical composition of PV steel.

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KW - neutron dosimetry

KW - pressure vessel surveillance

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U2 - 10.1520/STP10067S

DO - 10.1520/STP10067S

M3 - Conference contribution

AN - SCOPUS:85166388231

T3 - ASTM Special Technical Publication

SP - 115

EP - 120

BT - Reactor Dosimetry

A2 - Farrar, Harry

A2 - Lippincott, Ezra Parvin

PB - ASTM International

T2 - 6th ASTM-Euratom Symposium on Reactor Dosimetry: Methods, Applications, and Standardization

Y2 - 31 May 1987 through 5 June 1987

ER -

Analysis of First Pressure Vessel Surveillance Capsule from Krško Nuclear Power Plant

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Keywords

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