Innovations on life management of VVER reactor pressure vessels

Antero Tamminen, Jyrki Kohopää, Matti Valo, Jussi Solin

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

The embrittlement rate of the pressure vessel weld material is a dominating factor in life management of VVER reactor pressure vessels. In order to maintain adequate safety level, several backfitting measures have been performed in Loviisa. The neutron flux and embrittlement rate was reduced after receiving the first indications of anticipated problems. An increase of emergency core cooling water temperature and other process related changes followed to eliminate and reduce potential transients. Finally, the core weld of Loviisa 1 was successfully annealed in 1996. A current concern is to verify the post-annealing embrittlement rate in order to enable safe and economic life management of the RPV. Post-annealing re-embrittlement is governed by somewhat different mechanisms than the embrittlement of the first irradiation cycle. A new tentative approach for predicting the re-embrittlement rate has been proposed.
Original languageEnglish
Title of host publicationBALTICA V
Subtitle of host publicationCondition and Life Management for Power Plants
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages665-680
Volume2
ISBN (Electronic)951-38-5717-4
ISBN (Print)951-38-5716-6
Publication statusPublished - 2001
MoE publication typeA4 Article in a conference publication
EventBALTICA V - Condition and Life Management for Power Plants - Porvoo, Finland
Duration: 6 Jun 20018 Jun 2001

Publication series

SeriesVTT Symposium
Number212
ISSN0357-9387

Conference

ConferenceBALTICA V - Condition and Life Management for Power Plants
Abbreviated titleBaltica V
CountryFinland
CityPorvoo
Period6/06/018/06/01

Fingerprint

Embrittlement
Pressure vessels
Innovation
Welds
Annealing
Neutron flux
Cooling water
Irradiation
Economics

Keywords

  • innovation

Cite this

Tamminen, A., Kohopää, J., Valo, M., & Solin, J. (2001). Innovations on life management of VVER reactor pressure vessels. In BALTICA V: Condition and Life Management for Power Plants (Vol. 2, pp. 665-680). Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 212
Tamminen, Antero ; Kohopää, Jyrki ; Valo, Matti ; Solin, Jussi. / Innovations on life management of VVER reactor pressure vessels. BALTICA V: Condition and Life Management for Power Plants. Vol. 2 Espoo : VTT Technical Research Centre of Finland, 2001. pp. 665-680 (VTT Symposium; No. 212).
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Tamminen, A, Kohopää, J, Valo, M & Solin, J 2001, Innovations on life management of VVER reactor pressure vessels. in BALTICA V: Condition and Life Management for Power Plants. vol. 2, VTT Technical Research Centre of Finland, Espoo, VTT Symposium, no. 212, pp. 665-680, BALTICA V - Condition and Life Management for Power Plants, Porvoo, Finland, 6/06/01.

Innovations on life management of VVER reactor pressure vessels. / Tamminen, Antero; Kohopää, Jyrki; Valo, Matti; Solin, Jussi.

BALTICA V: Condition and Life Management for Power Plants. Vol. 2 Espoo : VTT Technical Research Centre of Finland, 2001. p. 665-680 (VTT Symposium; No. 212).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

TY - GEN

T1 - Innovations on life management of VVER reactor pressure vessels

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AU - Valo, Matti

AU - Solin, Jussi

PY - 2001

Y1 - 2001

N2 - The embrittlement rate of the pressure vessel weld material is a dominating factor in life management of VVER reactor pressure vessels. In order to maintain adequate safety level, several backfitting measures have been performed in Loviisa. The neutron flux and embrittlement rate was reduced after receiving the first indications of anticipated problems. An increase of emergency core cooling water temperature and other process related changes followed to eliminate and reduce potential transients. Finally, the core weld of Loviisa 1 was successfully annealed in 1996. A current concern is to verify the post-annealing embrittlement rate in order to enable safe and economic life management of the RPV. Post-annealing re-embrittlement is governed by somewhat different mechanisms than the embrittlement of the first irradiation cycle. A new tentative approach for predicting the re-embrittlement rate has been proposed.

AB - The embrittlement rate of the pressure vessel weld material is a dominating factor in life management of VVER reactor pressure vessels. In order to maintain adequate safety level, several backfitting measures have been performed in Loviisa. The neutron flux and embrittlement rate was reduced after receiving the first indications of anticipated problems. An increase of emergency core cooling water temperature and other process related changes followed to eliminate and reduce potential transients. Finally, the core weld of Loviisa 1 was successfully annealed in 1996. A current concern is to verify the post-annealing embrittlement rate in order to enable safe and economic life management of the RPV. Post-annealing re-embrittlement is governed by somewhat different mechanisms than the embrittlement of the first irradiation cycle. A new tentative approach for predicting the re-embrittlement rate has been proposed.

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PB - VTT Technical Research Centre of Finland

CY - Espoo

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Tamminen A, Kohopää J, Valo M, Solin J. Innovations on life management of VVER reactor pressure vessels. In BALTICA V: Condition and Life Management for Power Plants. Vol. 2. Espoo: VTT Technical Research Centre of Finland. 2001. p. 665-680. (VTT Symposium; No. 212).