Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning
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P. Poskas
, V. Simonis , A. Smaizys , A. Sirvydas , V. Ragaisis , R. Kilda and R. Zujus
Abstract
Unit 1 and Unit 2 reactors of the Ignalina Nuclear Power Plant were shutdown in December 31, 2004 and December 31, 2009, respectively. Preliminary and Final Decommissioning Plans for the Ignalina Nuclear Power Plant Units 1 and 2 were prepared, the latter of which was approved by Ministry of Economy in 2005. The main points of Final Decommissioning Plan and the main Decommissioning Projects for the Ignalina Nuclear Power Plant are summarized in this paper. Particular attention is drawn to the spent nuclear fuel and radioactive waste management projects. Preliminary analysis showed that the main mass of equipment to be dismantled is concentrated in reactor buildings (∼39%) and turbine halls (∼37%) and consists from metals of different types (∼83%). From radiological point of view, a major part (∼61%) of contaminated equipment can be classified as very low level radioactive waste.
Kurzfassung
Die Reaktoreinheiten 1 und 2 des Ignalina Kernkraftwerks waren am 31. Dezember 2004 bzw. am 31. Dezember 2009 stillgelegt worden. Einleitende und endgültige Stilllegungspläne waren vorbereitet und vom Wirtschaftsministerium 2005 genehmigt worden. Die Stilllegungspläne und die wichtigsten Stilllegungsprojekte für das Ignalina Kernkraftwerk werden in diesem Artikel zusammengefasst. Besondere Aufmerksamkeit richtet sich auf das Management von verbrauchtem Kernbrennstoff und radioaktivem Abfall. Die Analyse zeigte, dass die Hauptmasse der zu demontierenden Ausrüstung in den Reaktorgebäuden (∼39%) und Turbinenhallen (∼37%) konzentriert sind und aus Metallen verschiedener Art (∼83%) bestehen. Vom radiologischen Gesichtspunkt aus kann der Hauptteil (∼61%) der kontaminierten Ausrüstung als radioaktive Abfälle niedrigster Stufe klassifiziert werden.
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© 2011, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Overview of safety improvement during RBMK-1500 reactor core lifetime upgrading
- Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning
- Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant
- Preliminary evaluation of effect of Engineered Safety Features on source term for AHWR containment
- Burn up extension in a PBMR-400 full core using weapon grade plutonium fuel mixed with thorium
- A study on the damage of potential first wall materials in a nuclear fusion reactor using plutonium bearing salt
- An analytical benchmark of MYRRHA ADS in cylindrical geometry
- Dosimetric characteristics of three new design 125I brachytherapy sources
- Determination of 89Zr production parameters via different reactions using ALICE and TALYS codes
- Novel dose calculation and characterization of 32P intravascular brachytherapy stent source
- Cyclotron production of 85Sr by proton irradiation of natRb
- Lessons learnt from PSA for new and advanced reactors in Russia
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Overview of safety improvement during RBMK-1500 reactor core lifetime upgrading
- Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning
- Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant
- Preliminary evaluation of effect of Engineered Safety Features on source term for AHWR containment
- Burn up extension in a PBMR-400 full core using weapon grade plutonium fuel mixed with thorium
- A study on the damage of potential first wall materials in a nuclear fusion reactor using plutonium bearing salt
- An analytical benchmark of MYRRHA ADS in cylindrical geometry
- Dosimetric characteristics of three new design 125I brachytherapy sources
- Determination of 89Zr production parameters via different reactions using ALICE and TALYS codes
- Novel dose calculation and characterization of 32P intravascular brachytherapy stent source
- Cyclotron production of 85Sr by proton irradiation of natRb
- Lessons learnt from PSA for new and advanced reactors in Russia