Проаналізовано зв’язки між варіантом остаточного захоронення та потребами в довгостроковому зберіганні радіоактивних відходів з огляду на пропозиції щодо можливих змін схеми класифікації РАВ у цілях захоронення. Розглянуто концептуальний підхід до проектування сховищ для зберігання довгоіснуючих РАВ на майданчику комплексу виробництв «Вектор» та підходи щодо застосування вимог нормативних документів, принципів і критеріїв радіаційної безпеки в проектуванні сховищ для довготривалого зберігання РАВ та оцінки рівня їх безпеки.
Sealed radiation sources (SRS) are extensively used worldwide in agriculture, industry, medicine and different research areas.
If further use of SRS is not envisaged, and the decision is made on declaration of these disused SRSs (DSRS) as radioactive waste (RW), then legislative and regulatory requirements for RW management are fully applicable from that point.
Since DSRSs have essential distinctions from other types of RW, in particular, high specific activity, it is critically important to ensure safe management of DSRS, declared as RW, at all stages of their management including disposal. DSRS disposal as RW is the final phase of SRS lifecycle and final stage of their safe and reliable management.
In this paper, there are considered safety issues for management of DSRS, declared as RW. Approaches to DSRS disposal recommended by IAEA, advantages and drawbacks of different disposal options for DSRS are analyzed.
DSRS disposal needs shall be considered taking into account safety requirements for RW disposal. First, DSRS shall be attributed to specific RW class to address respective disposal needs. This is a challenging issue because the approaches for categorization of SRS and classification of RW are essentially different.
DSRS declared as RW may be disposed of either together with other RW in the existing or planned RW disposal facilities, or in the disposal facilities designed and constructed specially for DSRS.
Current situation with DSRS management in Ukraine is analyzed. DSRS management strategy in Ukraine envisages their long-term storage in the centralized facility for 50 years with subsequent transfer for disposal. At that, there are neither specified disposal facilities where DSRS will be disposed of, nor established generic waste acceptance criteria for DSRS disposal. Recommendations on further steps for solving challenging issues related to safe disposal of DSRS in Ukraine are provided.
Solution of a set of challenging issues related to DSRS management revealed in the paper will promote implementation of comprehensive approach to safe disposal of DSRS in Ukraine.
The paper considers the conservative scenario of potential exposure that envisages simultaneous destruction of barriers with simultaneous release of radionuclides by the example of Lot 3 near-surface radioactive waste disposal facility at the Vektor Industrial Complex located in the Chornobyl Exclusion Zone. A conceptual model that considers migration of radionuclides through the aeration zone and aquifer to the potable water well, as well as mixing of infiltration water containing radionuclides with ground water in case of reaching the aquifer, was developed to analyze the mentioned scenario. Permissible specific activity of radioactive waste in the facility is calculated under the assumption that radioactive waste contains only 90Sr radionuclide. Normalysa software is used for calculations.
A key point for safety assessments at different steps of radioactive waste (RW) management is the knowledge of all the relevant properties of materials that are to be disposed of as RW or cleared from regulatory control (immediately or after a certain period of time for decay storage). Characterization is the basis for the determination of radiological and non-radiological hazards of the radioactive materials and waste.
This paper considers approaches for a systemized characterization of radioactive waste at all steps of its management from generation to disposal. These approaches ensure safe radioactive waste management at each step and the compliance of the final radioactive waste product with the established requirements.
The provided information is based on the “Guideline for characterization, accounting and control of radioactive waste”, which was developed jointly by experts from SSTC NRS and RISKAUDIT.
Проаналізовано вимоги нормативних документів, відповідно до яких проектувалися та споруджувалися пункти захоронення радіоактивних відходів на майданчиках спеціалізованих комбінатів УкрДО «Радон», розглянуто підходи щодо застосування принципів та критеріїв радіаційної безпеки в процесі переоцінки безпеки цих пунктів.
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