Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant
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V. Ragaisis
Abstract
New solid radioactive waste management and interim storage facilities will be constructed for the Ignalina Nuclear Power Plant to support ongoing decommissioning activities, including removal and treatment of operational waste from the existing storage buildings. The paper presents approach and methods that have been used to assess radiological impacts to the general public potentially arising under normal operation and accident conditions and to demonstrate compliance with regulations in force. The assessment of impacts from normal operation includes evaluation of exposure arising from release of airborne radioactive material and from facilities and packages containing radioactive material. In addition, radiological impacts from other nearby operating and planned nuclear facilities are taken into consideration. The assessment of impacts under accident conditions includes evaluation of exposure arising from the selected design and beyond design basis accidents.
Kurzfassung
Neue Einrichtungen für feste radioaktive Abfälle und deren Zwischenlagerung werden für das Ignalina Kernkraftwerk gebaut, um die laufenden Stilllegungsaktivitäten, einschließlich der Entfernung und Behandlung der Abfälle der vorhandenen Lagergebäude zu unterstützen. Der Beitrag beschreibt den verwendeten Ansatz und die Methoden, um die radiologischen Konsequenzen für die allgemeine Bevölkerung zu bewerten, die sich beim normalen Betrieb und unter Unfallbedingungen ergeben und die Einhaltung bestehender Vorschriften zu demonstrieren. Die Bewertung der radiologischen Konsequenzen für die allgemeine Bevölkerung beim normalen Betrieb umfasst die Bestimmung der Exposition, die sich aus der Freisetzung radioaktiver Materialien und aus Einrichtungen und Verpackungen radioaktiver Materialien ergibt. Außerdem werden radiologische Konsequenzen anderer in der Nähe befindlicher Kernwerke, in Betrieb bzw. geplant, mit berücksichtigt. Die Bewertung radiologischer Konsequenzen unter Unfallbedingungen umfasst die Bestimmung der Expositionen aufgrund des gewählten Designs und von Auslegungsstörfällen.
References
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© 2011, Carl Hanser Verlag, München
Artikel in diesem Heft
- 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
Artikel in diesem Heft
- 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