Development of a decommissioning strategy for the MR research reactor
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B. Bylkin
Abstract
A description of the selected decommissioning strategy for the research reactor MR at the site of the Kurchatov Institute in Moscow is presented. The MR reactor hall is planned to be used as a temporary fuel store for the other research reactors on the site. On the basis of the site-specific conditions and overall decommissioning goals, it was identified that phased immediate decommissioning is the preferable option. The current status of the reactor, expected final conditions and the sequence of decommissioning works are shown.
Kurzfassung
Eine Beschreibung der ausgewählten Stilllegungsstrategie für den MR Forschungsreaktor auf dem Gelände des Kurchatov Instituts in Moskau wird vorgestellt. Es ist geplant, die MR Reaktorhalle als Brennelemente-Zwischenlager für die anderen Forschungsreaktoren auf dem Gelände zu nutzen. Auf der Grundlage geländespezifischer Bedingungen und übergreifender Stilllegungsziele wurde festgelegt, dass die sofortige schrittweise Stilllegung die beste Lösung ist. Der derzeitige Zustand des Reaktors, die erwarteten endgültigen Gegebenheiten und die Abfolge der Stilllegungsarbeiten werden aufgezeigt.
References
1 Ponomarev-Stepnoy, N. N., et al.: Decommissioning of research reactor facilities at RRC Kurchatov Institute. Proc. of the International Conference “Research reactors in the 21st century” Moscow, June 20–22, 2006Search in Google Scholar
2 Selection of Decommissioning Strategies: Issues and Factors. IAEA-TECDOC-1478, Vienna, IAEA (2005)Search in Google Scholar
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© 2010, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- European clearinghouse on nuclear power plants operational experience feedback
- Investigation on primary side oriented accident management measures in a hypothetical station blackout scenario for a VVER-1000 pressurized water reactor
- Heat transfer to the building structures of the Ignalina NPP accident localisation system
- Algorithmic determination of fuel rod cladding burst time at elevated temperatures
- Development of a decommissioning strategy for the MR research reactor
- Neutron transmutation doping conceptual design
- Design optimization of shell-and-tube heat exchangers using single objective and multiobjective particle swarm optimization
- Chebyshev polynomials expansion method for solving the one-dimensional transport equation in spherical geometry
- Heuristic geometric “eigenvalue universality” in a one-dimensional neutron transport problem with anisotropic scattering
- An analytical solution for the one-dimensional time-dependent SN transport equation for bounded and unbounded domains in cartesian geometry
- Accurate critical slab calculations for various degrees of anisotropy and for different reflection coefficients
- Technical Notes/Technische Mitteilungen
- The boundary problem in the 1D-CANDLE burn-up reactor
