Surveillance Programs and Irradiation Embrittlement Research of the Loviisa Nuclear Power Plant

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PAPERS REVIEWED regarding SURVEILLANCE

Which were the reviewed papers on surveillance practice?

ANSWER

Surveillance programs and irradiation embrittlement research of the Loviisa nuclear power plant

R. Ahlstrand, K. Törrönen, M. Valo, B. Baers

Surveillance Embrittlement of Nuclear Pressure Vessel Steels: An International Review (Second Volume), ASTM STP 909 (1986) p. 55-69

Realization of work on the NPP equipment metal condition survey with the purpose of prolongation of its service life

J. Brynda, M. Brumovsky

NPP life Management p. 19

Standard and modified surveillance programme for WWER-1000 RPV materials

J. Brynda, M. Brumovsky

NPP life Management p. 19

Consolidation of scientific and technological expertise to assess the reliability of reactor pressure vessel embrittlement prediction in particular for the arctic area plant (COBRA)

A. Ballesteros, J. Bros, L. Debarberis, F. Sevini, D. Erak, S. Gezashchenko, A. Kryukov, A. Shtrombakh, S. Goloschapov, Ionov, Y. Pytkin, Y. Anikeev, G. Banyuk, A. Plush, F. Gillemot, L. Tatar, V. Petrosyan

Nuclear Engineering and Design 235(2005) p. 411-419

Assessmen of irradiation conditions in WWER-440(213) RPV surveillance position

ICONE 12, 12th Int. Conf.on Nuclear Engng., April 25-29,2004, USA, paper 49477

Surveillance Specimen Programmes for WWER reactor vessels in the Czech Republic

M. Brumovsky, O. Erben, M. Kytka, P. Novosad

Int.Symposium FONTEVRAUD 5, 23-27 Sept.2002,

Surveillance of WWER-440C reactor pressure vessels

M. Brumovsky, T.Pav

Radiation Embrittlement of Nuclear Reactor Pressure vessel Steels: An International Review(Fourth Volume), ASTM STP 1170, 1993, p. 57-70

Surveillance programme for WWER-440/type 213 reactor pressure vessels - Standard programme, re-evaluation of results, supplementary programme

M. Brumovsky, P. Novosad, J. Zdarek

Effects of Radiation on Materials, 17th Int.Symposium, ASTM STP 1270,1996, p.522

Comparison of static and dynamic transition temperature shifts in VVER reactor pressure vessel steels

M. Brumovsky, M. Falcnik, M. Kytka, J. Malek, P. Novosad

Effects of Radiation on Materials, 19th Int.Symposium, ASTM STP 1366, 2000, p. 56

Supplementary survellance programme for reactor pressure vessels of VVER-440/V-213C type reactors in NPP Dukovany

M. Brumovsky, O. Erben, P. Novosad

Effects of Radiation on Materials, 19th Int.Symposium, ASTM STP 1366, 2000, p. 220

Supplementary survellance programme for WWER-440/V-213C reactors

M. Brumovsky, O. Erben, P. Novosad

Proceedings of ICONE 5; 5th Int.Conference on Nuclear Engineering, May 26-30, 1997, Nice, p. 1

Problems in a standard surveillance programme of WWER-1000 reactor pressure vessels

M. Brumovsky, C-Y. Rieg

IAEA meeting on Irradiation Embrittlement and Mitigarion, Espoo, Finland, October 23-26,1995, IWG-LMNPP-95/5

Aging Significantly at Termelin Start – Up Process

M. Brumovsky, J.Hahn, J.Zdarek

Life Management Activities for NPP’s in Czech Republic

M. BRUMOVSKY

Neutron Dosimetry in EDF Experimental Surveillance Peogramme for WWER-440 Nuclear Power Plants

M. Brumovsky, О. Erben, P. Novosad, L. Zerola, J. Hogel, J.P. Massoud, C. Trollat

Procedure for Determination action of Irradiation Embrittlement Trend Curves

M Falcnik, P. Novosad, M. Kytka and M. Brumovsky

Surveillance Specimen Programmes for WWER reactor vessels in the Czech Republic

Brynda J.,Hogel J., Brumovsky M.

Trans.17th Int.Conf.on Structural Mechanics in Reactor Technology (SMIRT 17), Prague, August 17-22(2003), paper G02-5

VVER Reactor Pressure Vessel Materials Database and Monitorig of Ageing and Lifetime Evalution

Jiri Brynda, Vladimir Cerny, Radek Konop

Specific nuclear reactors and associated plants p. 21

Tests of surveillance specimen containers for VVER-1000 reactor pressure vessel on cyclic strength with the aim to assure their operation lifetime

E.M. Bykov, V.S. Popadchuk, R. Yu. Zhukov, A.M. Ponomarev

3rd NTK on "Assurance of NPPs with WWER", Podolsk, Russia, 26-30 May 2003, Vol.2, p. 96

Irradiation-induced structural changes in surveillance material of VVER-440-type weld metal

M. Grosse, M. Denner, J. Boehmert, M.H. Mathon

J.of Nuclear Materials, 277(2000) p. 280-287

Extended analysis of VVER-1000 surveillance data

A. Kryukov, D. Erak, L. Debarberis, F. Sevini, B. Acosta

Int.J.Pressure Vessels and Piping 79(2002) p. 661-664

The properties of WWER-1000 type materials obtained on the basis of a surveillance program

A. Kryukov, Yu. Nikolaev

Nucl.Engng. And Design 195(2000) p. 143-148

Irradiation embrittlement monitoring of WWER-440/213 tzpe RPVs

L. Kupca, P. Beno

Nucl. Engng. And Design 196(2000) p. 81-91

Irradiation embrittlement monitoring programmes in the Slovak Republic nuclear power plants

L. Kupca

Int.Symposium FONTEVRAUD 5, 23-27 Sept.2002,

Radiation Embrittlement of Cr–Ni–Mo and Cr–Mo RPV Steels

Yu. A. Nikolaev1

Journal of ASTM International, Vol. 4, No. 8

Changes in magnetic parameters of neutron irradiated RPV Linde80 high copper weld surveillance specimens

Kee-Ok Chang, Se-Hwan Chi, Kwon-Jae Choi, Byeong-Chul Kim, Sam-Lai Lee

International Journal of Pressure Vessels and Piping 79 (2002) p. 753–757

Neutron embrittlement of VVER reactor pressure vessels—recent results, open issues and new developments

R. Ahlstrand, M. Bièth, C. Rieg

Nuclear Engineering and Design 230 (2004) p. 267–275

Radiation embrittlement of VVER-440 reactor vessel - Finnish experience

R.Ahlstrand, H.Jokineva, J. Kohopaa

Nuclear Europe Worldscan Journal Article

Radiation stability of WWER-440 vessel materials

A.D. Amayev, A.M. Kryukov, V.I. Levit, M. A. Sokolov

An international review (Fourth Volume). Philadelphia, PA (United States). American Society for testing and Materials. 1993. 414p. 9-29

New TACIS regional projects on radiation embrittlement and integrity assessment of WWER reactor pressure vessels

M. Bieth, C. Rieg, R. Ahlstrand

International Journal of Pressure Vessels and Piping 81 (2004) p. 677–682

Surveillance specimen programmes for WWER reactor pressure vessel in the Czech Republic

M. Brumovsky, O. Erben, M. Kytka, P. Novosad, J. Brynda

Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors 1175p. 765-776 5 international symposium 23-27 Sep 2002

Reevaluation of irradiation embrittlement of surveillance specimens

M. Brumovgsky, P. Novosad, M. Falcnik, M. Kytka, M. Vacek, J. Malek

Nucleon 3, 1998 p. 9-12

Kozloduy NPP Unit 1 reactor Pressure Vessel Boat Sampling

M. Cvitanovic, G. Krpanec

Pragur, czech Republic, 8-10 December, 1997

PTS AND THE IAEA DATABASE

LM. Davies, F. Gillemot, V. Lyssakov

Analysis of WWER-440 and PWR RPV welds surveillance data to compare irradiation damage evolution

L. Debarberis, B. Acosta, A. Zeman, F. Sevini, A. Ballesteros, A. Kryukov, F. Gillemot, M. Brumovsky

Journal of Nuclear Materials xxx (2006) xxx–xxx

Main Achivements of the TACIS R2.06/96 Project: Surveillance Program for VVER 1000 Reactor Pressure Vessels

R.Gérard, G.Karzov, B.Margolin, J.Shtrombakh, S.Zaritsky, V.Vasiliev R.Langer, E.Van Walle

5 International symposium Fontevraud - Royal Abbey (Fance) 23-27 Sep 2002

Extension of the Surveillance Program at NPP PAKS

F.Gillemot

Proceedings of a specialists meeting. Working material 1992 144 p.68-75

R&D Background for Life Management in Hungary

F.Gillemnot, T.Fekete, L.Tatr, M.Horvth

IAEA-CN-92/P6

Plant Life Management in Hungary

F. Gillemot

IAEA specialists meeting on strategies and policies for nuclear power plant life management vienna (Austria) 28-30 September 1998

IAEA Post Irradiation Examination Facilities Database

K. Hakon, J. Jenssen, P. Blanc, P. Dubuisson, R. Manzel, A. Egorov

"HOTLAB" Plenary Meeting 2004 September 6-8 Halden Norway

Determination of fast neutron fluence in surveillance specimens of unit 1 NPP Khmelnitski

V. Vorobej, G. Paralo, A. Titov, S. Shadrincev

Extended analysis of VVer-1000 surveillance data

A. Kryukov, D. Erak, L. Debarberis, F. Sevini, B. Acosta

Irradiation Embrittlement Monitoring Programmes in the Slovak Republic Nuclear Power Plants

Ľ. Kupča,

Progress of irradiation embrittlement monitoring in the Slovak Republic NPP`s

L. Kupca, P. BEÒO

1-stAMES Biennial Conference on : “Through life toughness prediction in reactor steels“ HevízHungary 6-thto 8-thFebruary 2006

Extended analysis of VVER-1000 surveillance data

A. Kryukov, D. Erak, L. Debarberis, F. Sevini, B. Acosta

International Journal of Pressure Vessels and Piping 79 (2002) p. 661–664

Surveillance Programs and Irradiation Embrittlement Research of the Loviisa Nuclear Power Plant

R. Ahlstrand, K. Toeroenen, M. Valo, B.Baers

An International Review (Second Volume), ASTM STP 909, L. E. Steele, Ed., American Society for Testing and Materials, Philadelphia, 1986, p. 55-69

Assessment of Irradiation Conditions in WWER-440/213 RPV Surveillance Location

A. ballesteros, J. Bros, L. Debarberis, F. Sevini, D. Erak, S. gezashchenko, A. Kryukov, Y. Shtrombakh, S. Goloschapov, A. Ionov, Y. Pytkin, Y. Anikeev, G. Banyuk, A. plusch, F. Gillemot

Proceedings of ICONE 12 12th International Conference on Nuclear Engineering Aptil 25-29,2004, Arlington Virginia USA

Surveillance of WWER-440C reactor pressure vessels

M. Brumovsky, T. Pav

An International review (Fourth Volume) Philadelphia PA (United States) American Society for Testing and Materials 1993 414 p. 57-70

Surveillance program for WWER-440/ Type 213 reactor pressure vessel- standard program, re-evaluation of results, supplementary program

M. Brumovsky, P. Novosad, J. Zdarek

17. symposium on effects of radiation on materials. Sun Valley, ID (United States). p. 20-23 Jun 1994

Supplementary Surveillance Program for Reactor Pressure Vessel of VVER-440/V-213C Type Reactors in NPP Dukovany

M. Brumovsky, O. Erben, P. Novosad

Effects of Radiation on Material: 19th International Symposium, ASTM STP 1366 American Society for Testing and Materials, West Conshohocken, PA 2000

Problems in a Standard Surveillance Programme of WWER-1000 Reactor Pressure Vessel

M. Brumovsky, C.Y. Rieg

to be presented at the IAEA Specialists Meeting on Irradiation Embrittlement and Mitigation to be held on 23-27 October 1995 in Helsinki, Finland

Surveillance Specimen Programs for WWER type Reactors

Milan BRUMOVSKY

Proceedings of PVP 2005 ASME Pressure Vessels and Piping Division Conference July 17-21, 2005, Denver, Colorado USA

Surveillance specimen programmes for WWER reactor pressure vessel in the Czech Republic

J. Brynda, J. Hogel, M. Brumovsky

17 th international conference on structural mechanics in reactor technology Prague (Czech Republic) 17-22 Aug. 2003

Recent development in Life Management of the Pressurised Components

F. Gillemot

Technical Committee Meeting of the International Working Group on Life Management of Nuclear Power Plants Vienna 6-8 October 1997

The properties of WWER-1000 type materials obtained on the basis of surveillance program

A.M. Kryukov, Yu.A. Nikolaev

Nuclear Engineering and Design 195 (2000) p. 143–148

Irradiation Embrittlement Monitoring Programs of RPV’s in the Slovak Republic NPP’s

L. Kupca

Proceedings of ICONE14 International Conference on Nuclear Engineering July 17-20, Miami, Florida, USA

Atom probe tomography of 15Kh2MFA Cr-Mo-V steel surveillance specimens

M.K Miller, K.F Russell, J. Kocik E. Keilova

Micron 32 (2001) p. 749-755

Embrittlement of low copper VVER 440 surveillance samples neutron-irradiated to high fluence

M.K. Miller, K.F. Russel, J. Kocik, E. Keilova

Journal of Nuclear Materials 282 (2000) p. 83-88

Radiation Embrittlement of Cr–Ni–Mo and Cr–Mo RPV Steels

Yu. A. Nikolaev

Journal of ASTM International, Vol. 4, No. 8 Paper ID JAI100695

Supplementary surveillance program

P. Novosad, M. Falcnik, M. Kytka, M. Brumovsky

Nucleon 3 1998 p. 13-17

Neutron Dosimetry in EDF Experimental Surveillance Programme for WWER-440 Nuclear Power Plants

M. Brumovsky, O. Erben, P. Novosad, L. Zerola, J. Hogel, J.P. Massoud, C. Trollat

9. internationale conference on nuclear engineering Nice Acropolis (France) 8-12 Apr. 2001

Results on research of templates from Kozloduy-reactor pressure vessel

P. Platonov Ja. Shtrombakh, A. Kryukov, B. Gurovich, Ju. Korolev J. Shmidt

Nuclear Engineering and Design 191 (1999) p. 313–325

Monitoring of Radiation Embrittlement of the First and Second Generation of VVER RPV Steels

Ya. I. Shtrombakh and Yu.A. Nikolaev