Decommissioning the Research Nuclear Reactor VVR-S Magurele –Bucharest: Analyze, Justification and Selection of Decommissioning Strategy

Dragusin, M.; Popa, Vasile; Boicu, Alin; Tuca, Carmen; Iorga, I.; Mustata, C.

doi:10.1142/9789812702579_0031

Cited by 2 publications

(4 citation statements)

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“…137 Cs is the "key nuclide" for fission products [1,11]. In the case of hardly detectable radionuclides, specific and total activity can be calculated using the method of scaling factors, having as the reference 60 Co radionuclide (major activation product) and 137 Cs (fission product).…”

Section: Strategies Associated With Radioactive Waste Characterizationmentioning

confidence: 99%

“…To estimate correction factors, theoretical calculations, results from measurements of gamma spectrometry and literature data can be used [11]. In Table I the potential radionuclides involved in the contamination/activation of the protection and control rods, as part of the VVR-S structural components, are presented [1]. Two methods can be used for radiological characterization of the waste: (i) destructive analysis, which can provide precise information about the radionuclides from the materials, (ii) non-destructive analysis, which is challenging because of the potentially high degree of variability from item to item.…”

Section: Strategies Associated With Radioactive Waste Characterizationmentioning

confidence: 99%

“…The decommissioning of the reactor has started in 2010 and is planned to be finalized in 2020. It is the first nuclear research reactor from the South-East of Europe that has started the decommissioning project [1].…”

Section: Introductionmentioning

confidence: 99%

“…The reactor control was carried out by means of nine rods, placed in the central part of the core; 4 rods were used for the manual control of power, 1 for automatic control, 3 rods for reactor safety (emergency rods) and 1 for the fine control of power [1][2]. The dismantling of * corresponding author; e-mail: johnny@nipne.ro the activated-contaminated control rods was performed in the second phase of the research reactor decommissioning project.…”

Section: Introductionmentioning

confidence: 99%

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Role of Operational Radioprotection Simulation in the Dismantling of the Protection and Control Rods of VVR-S Reactor

et al. 2017

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The VVR-S nuclear research reactor owned by Horia Hubulei National Institute of Physics and Nuclear Engineering, has functioned between 1957 and 1997 at a nominal thermal power of 2 MW, using less-enriched nuclear fuel (10%), type EK-10, and highly enriched fuel (36%), type S-36. The reactor control was carried out by means of nine rods placed in the central part of the core. Four rods were used for the manual control of power, one for automatic control, three rods for reactor safety (emergency rods) and one for the fine control of power. One of the high hazard operations was the dismantling of the activated-contaminated control rods. Because of a higher radiological risk, simulation was performed to determine the expected maximum dose. The maximum gamma dose rate obtained using simulated results was 3.5 Sv/h, for the highly activated rod. In the real measurement, when the work was performed, the maximum gamma dose rate was 3 Sv/h.90 Sr+ 90 Y are expected to be present in the control rods radioactivity.

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Section: Strategies Associated With Radioactive Waste Characterizationmentioning

confidence: 99%

Section: Strategies Associated With Radioactive Waste Characterizationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Role of Operational Radioprotection Simulation in the Dismantling of the Protection and Control Rods of VVR-S Reactor

et al. 2017

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Overview of less advanced programmes and their requirements

Diaconu¹,

Ivanov

Železnik³

et al. 2015

Mineral. mag.

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Geological disposal (GD) of radioactive waste is close to becoming a reality for Finland, Sweden and France. High-technology development and advanced knowledge has made it possible to defend the feasibility and the safety of such facilities, making the European Union a leader in the field. Other European countries are closely behind, developing high competence through advanced research programmes, research infrastructures and public engagement.At the other extreme, there are countries whose GD programmes are at an early stage and no systematic research programmes exist. These include several new Member States but not the Czech Republic and Hungary, both of which have already initiated a siting process.There are several common reasons for this delay in schedule: small and relatively younger nuclear energy programmes, return of the spent fuel (especially from research reactors) to the countries of origin, open fuel cycle concept (requiring at least 50 years of wet and dry storage). In this context, there has been little pressure on setting up an early GD programme. Currently their disposal concepts are only generic and in most of these countries need updating, taking into account the current socio-economic context.However, some of these new Member States still aim to have a GD in operation within several decades, e.g. 2055 in Romania and 2067 in Slovenia. Strategic planning based on the experience of more advanced programmes shows the GD process should start immediately in order to be able to achieve these deadlines.In this context, the implementation of the EC Directive 70/2011 gives the opportunity to progress the advancement of the GD process in these countries.

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Decommissioning the Research Nuclear Reactor VVR-S Magurele –Bucharest: Analyze, Justification and Selection of Decommissioning Strategy

Cited by 2 publications

References 0 publications

Role of Operational Radioprotection Simulation in the Dismantling of the Protection and Control Rods of VVR-S Reactor

Role of Operational Radioprotection Simulation in the Dismantling of the Protection and Control Rods of VVR-S Reactor

Overview of less advanced programmes and their requirements

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