Pre-decommissioning complex engineering and radiation inspection of the WWR-M reactor
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Yu. N. Lobach
Abstract
The Kiev's research reactor WWR-M has been in operation for more than 50 years. Decommissioning plan should to be prepared and approved before the beginning of the decommissioning activities. A key activity during reactor operation is implementing the pre-decommissioning complex engineering and radiation inspection. It should be done with objective to collect, arrange and analyze the data related to the engineering and radiation conditions of the reactor systems and equipment. Recently, such an inspection has been completed. The analysis of available documentation has consisted in the assessment of design, construction, technological, assembling, operation, maintenance and repair documentation for each system. The radiation survey was performed in two different ways, namely, by doing the experimental measurements and by performing calculations. The collected data are provided a comprehensive technical basis for the development of decommissioning documentation which is required for the planning and implementation of the reactor decommissioning.
Kurzfassung
Der Forschungsreaktor WWR-M ist seit mehr als 50 Jahren in Kiev in Betrieb. In Übereinstimmung mit den existierenden gesetzlichen Vorgaben soll nun ein Rückbauplan vorbereitet und nach Genehmigung durch die Aufsichtsbehörden mit dem Rückbau begonnen werden. Ein wesentlicher Bestandteil zur Vorbereitung des Rückbaus ist die umfassende Aufnahme der Strahlungs- und Engineeringsituation des Reaktors. Erst danach ist eine Detailplanung möglich. Diese Phase ist für den WWR-M abgeschlossen und ihre Ergebnisse werden im vorliegenden Beitrag beschrieben.
References
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© 2014, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- A model-based approach to operational event groups ranking
- Application of the method for uncertainty and sensitivity evaluation to results of PWR LBLOCA analysis calculated with the code ATHLET. Part 2: sensitivity analysis
- Statistical Large-Break LOCA analysis for PWRs with combined ECC injection
- Analysis of the CSF model for simulated loss of coolant accident conditions
- Performance of two fluid model based numeric tool with pressure and enthalpy as independent variables for simulation of two phase flow in axial and radial direction
- Pre-decommissioning complex engineering and radiation inspection of the WWR-M reactor
- Analysis of the source term formation in a severe accident initiated by end fitting failure in CANDU type reactors
- Neutron flux investigation on certain alternative fluids in a hybrid system by using MCNPX Monte Carlo transport code
- Analytical investigation of lignite and its ash samples taken from the Afşin-Elbistan coal basin in Turkey
- Explicit formulation of a nodal transport method for discrete ordinates calculations in two-dimensional fixed-source problems
- T1 and U1 approximations to neutron transport equation in one-dimensional spherical geometry
