Блог о ядерной и радиационной безопасности

С.Н. Богдан, к.т.н., О.М. Ковалевич, д.т.н., А.А. Хамаза, С.А. Шевченко, к.т.н. (ФБУ «НТЦ ЯРБ»).

Расчётное моделирование переходных процессов и аварий, потенциально возможных при эксплуатации объектов использования атомной энергии (ОИАЭ), является необходимым элементом обоснования ядерной и радиационной безопасности таких объектов. Разрабатываемые для этих целей программные средства (ПС)требуют проведения большого круга исследований с целью обоснованности использования реализованных в ПС расчетных методов и методик. В странах с развитой ядерной энергетикой органами государственного регулирования безопасности при использовании атомной энергии предусматривается обязательная оценка применимости (экспертиза) таких ПС, которую проводят либо специалисты самого органа государственного регулирования, либо специалисты организации научно-технической поддержки, формулирующие по итогам экспертизы выводы об области и условиях применимости того или иного ПС. Такой подход соответствует требованиям стандарта МАГАТЭ GS-G-1.2 «Рассмотрения и оценки, проводимые регулирующим органом для ядерных установок».

Вплоть до второй половины 80-х годов прошлого века специалисты Госатомнадзора СССР при оценке ПС могли руководствоваться только требованиями государственных стандартов. Однако действовавшие в то время ГОСТы устанавливали требования в основном к потребительским качествам ПС (простота освоения, удобство применения, быстродействие, надежность и т.д.), оставляя в стороне требования к реализуемым в ПС расчётным моделям, используемым для решения научных и инженерных задач. Современные стандарты, например, тоже не дают ответа на вопрос – как доказать способность ПС адекватно моделировать поведение таких сложных объектов, как ОИАЭ. Острота этого вопроса многократно усилилась после Чернобыльской аварии. При этом в атомной отрасли сложилось понимание того, что регулирующий орган совместно с ведущими специалистами научных и проектно-конструкторских организаций отрасли, должен оценивать и признавать возможность использования ПС при обосновании безопасности, для чего и была в 1991 г. создана система аттестации ПС.

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Курындин А.В., к.т.н. (kuryndin@secnrs.ru), Строганов А.А., к.ф.-м.н. (stroganov@secnrs.ru), Киркин А.М. (kirkin@secnrs.ru), Ляшко И.А. (lyashko@secnrs.ru), Курбатова М.В. (mkurbatova@secnrs.ru) (ФБУ «НТЦ ЯРБ»).

В статье приведено описание методов и подходов, принятых при разработке руководства по безопасности «Радиационные и теплофизические характеристики отработавшего ядерного топлива водо-водяных энергетических реакторов и реакторов большой мощности канальных» (РБ-093-14), а также описание разработанного на его основе программного комплекса «Калькулятор радиационных и тепло-физических характеристик ОЯТ». Даны конкретные примеры использования программного комплекса и продемонстрированы его возможности при решении задач по оценке радиационных и теплофизических характеристик отработавшего ядерного топлива реакторов ВВЭР-1000, ВВЭР-440 и РБМК-1000.

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Software SNF calculator based on safety guide radiation and thermal characteristics of VVER and RBMK spent nuclear fuel (RB-093-14)

Kuryndin A., Ph. D., Stroganov A., Ph. D., Kirkin A., Lyashko I., Kurbatova M. («SEC NRS»).

Methods and approaches used in the developed safety guide «Radiation and thermal characteristics of VVER and RBMK spent nuclear fuel» (RB-093-14) are presented in this paper. Software “Radiation and thermal characteristics Calculator of spent nuclear fuel”, based on safety guide (RB-093-14), is describes in this paper too. Moreover specific examples of its using and demonstration of its versatility during solving the problems of estimating radiation and thermal characteristics of VVER-1000, VVER-440 and RBMK-1000 spent nuclear fuel also shown in this paper.

Савельева Е.А., к.ф-м.н. (esav@ibrae.ac.ru) (Институт проблем безопасного развития атомной энергетики РАН).

В работе рассматриваются вопросы разработки специального программного комплекса, направленного на учет и анализ неопределенностей, связанных с параметрическим наполнением расчетно-прогностических моделей, использующихся при обосновании безопасности пунктов захоронения радиоактивных отходов, включая особые РАО.

Основные задачи данного комплекса состоят в создании модельно-независимых средств для анализа чувствительности расчетных моделей к изменению их параметров и оценке неопределенности результатов расчетно-прогностического моделирования. Сформулированы основы формирования такого программного комплекса.

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The concept of software system to assess uncertainties at safety demonstration of RW disposal facilities

Savel’eva Е., Ph. D. (esav@ibrae.ac.ru) (Nuclear Safety Institute of the RAS (IBRAE)).

This paper addresses the specialized software system development designed to account and analyse uncertainties related with the parametric content of calculation and predictive models applied in the course of safety demonstration of RW disposal facilities (including special RW).

This system basic purpose is to create the simulative-independent means for calculation models sensitivity analysis to their parameters changing and uncertainty assessment regarding calculation and predictive simulation results. Basis for such system creation is formulated.

Скворцов И.В. (Skvortsov.ivan.68@gmail.com), Белова Е.В., к.х.н. (bl174@bk.ru), Никитина Ю.В. (nikitinayulia1616@gmail.com) (ИФХЭ РАН), Родин А.В., к.х.н. (rodin@secnrs.ru) (ФБУ «НТЦ ЯРБ»), Зильберман Б. Я., д.т.н. (zby@mail.ru), Голецкий Н.Д., к.х.н. (goletsky@khlopin.ru) (АО «Радиевый институт имени В.Г. Хлопина).

Исследована динамика газовыделения при окислении 30%-ных растворов ТБФ в разбавителе С13 – водный раствор 12 моль/л HNO₃ в температурном интервале от 90°С до 110°С. Экспериментально определены кинетические параметры термохимического взаимодействия HNO₃ с компонентами органических растворов ТБФ в С13 в открытых сосудах для последующей оценки взрывоопасности данных систем в условиях экстракционной переработки высокоактивных материалов. Определено влияние предварительного облучения системы на кинетику термолиза.

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The dynamics of gas release at oxidation of TBP solution in diluent C13 in two phase systems

Skvortsov I., Belova E., Ph.D, Nikitina Y. (IPCE RAS), Rodin A., Ph.D (SEC NRS), Zilberman B., Ph.D, Goletskii N., Ph.D (Khlopin Radium Institute).

The dynamics of gas release at oxidation of 30% TBP solution in diluent C13 by aqueous solution of 12 mol/l of HNO₃ at a temperature from 90°C to 110°C was studied. The experimentally determined kinetic parameters of HNO₃ interaction with components of organic TBP solutions in diluent C13 at atmospheric condition for subsequent evaluation of explosion hazards of these systems at reprocessing of spent nuclear fuel. The effect of prior radiation exposure of system on the kinetics of thermolysis was determined.

Курындин А.В., к.т.н. (kuryndin@secnrs.ru), Строганов А.А., к.ф.-м.н. (stroganov@secnrs.ru), Киркин А.М. (kirkin@secnrs.ru), Карякин М.Ю. (karyakin@secnrs.ru) (ФБУ «НТЦ ЯРБ»).

В работе приведены результаты расчетного исследования температурных режимов конструкционных элементов ТУК-153, загруженного ОЯТ реакторов ВВЭР-1000, а также результаты расчетно-экспериментальных исследований, проведенных с целью верификации методов и подходов, использованных при создании расчетных моделей.

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Computational and experimental study of temperature condition of cask TUK 153 loaded with VVER-1000 SNF

Kuryndin A., Ph. D., Stroganov A., Ph. D., Kirkin A., Karyakin M. (SEC NRS).

This paper presents the results of computational study of temperature condition of cask TUK-153 loaded with VVER-1000 SNF and results of computational and experimental study performed to justify methods and approaches used in computational models.

Дживанова З.В. (zdzhivanova@ya.ru), Белова Е.В., к.х.н. (bl174@bk.ru) (ИФХЭ РАН), Соколов И.П., д.х.н. (sokolov@secnrs.ru), Родин А.В., к.х.н. (prodin@secnrs.ru) (ФБУ «НТЦ ЯРБ»).

Определены содержание карбоновых кислот в облученном ускоренными электронами экстрагенте в диапазоне доз 250 – 750 кГр, влияние регенерации на концентрацию карбоновых кислот, зависимости давления в экстракционной системе при протекании неуправляемых химических реакций азотной кислоты с карбоновыми кислотами для деградированных и регенерируемых растворов ТБФ в Изопаре-М.

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About reducing the content of the carboxylic acid at regeneration of degraded extractant

Dzivanova Z., Belova E., Ph.D. (IPCE RAS), Sokolov I., Ph.D., Rodin A., Ph.D. (SEC NRS).

The content of carboxylic acids in irradiated by accelerated electrons extractant in the range of 250 – 750 kGr was defined. The regeneration influence at the concentration of carboxylic acids was investigated. Relations of pressure for extraction system in case of runaway reactions of nitric acid with carboxylic acids flowing for degraded and regenerated solutions of TBP in Isopar-M.

Павлов Д.И.; д.т.н. Сорокин В.Т., info@atomproekt.com, АО «АТОМПРОЕКТ»; д.т.н. Гатауллин Р.М., mail@345mz.ru, АО «345 механический завод»; к.т.н. Шарафутдинов Р.Б., charafoutdinov@secnrs.ru, ФБУ «НТЦ ЯРБ».

Приведены конструкционные материалы, применяемые при изготовлении контейнеров для радиоактивных отходов всех классов. Представлены номенклатура и характеристики используемых и разрабатываемых контейнеров на предприятиях отрасли. Показаны варианты кондиционирования радиоактивных отходов 1 – 4 классов. Сформулированы направления создания парка контейнеров.

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The state and main directions of creating a fleet of containers for conditioning and disposal of radioactive waste

Pavlov D.; Sorokin V., Ph. D. (JSC «ATOMPROEKT»); Gataullin R., Ph. D. (JSC «345 mechanical plant»); Sharafutdinov R., Ph. D. (SEC NRS).

The structural materials, used in the production of containers for all classes of radioactive waste, are given in the article. The nomenclature and characteristics of containers, which used and develop in the industry, are shown. In the article are also presented the options for conditioning of 1 – 4 classes of radioactive waste and are formulated the ways for containers‘ fleet creation.

Хомяков А.П., д.т.н., ural-nrs@gosnadzor.ru; Морданов С.В., Никулин В.А., к.т.н., news@urfu.ru, ФГАОУ ВПО «Уральский федеральный университет имени первого Президента России Б.Н. Ельцина»; Корченкин К.К., к.т.н.; Мелентьев А.Б., к.х.н., mayak@po-mayak.ru, ФГУП «ПО «Маяк».

Представлены результаты исследований процессов усреднения химического состава и радиационной активности технологических азотнокислых растворов урана в емкостях приема азотнокислых растворов урана в процессе их подготовки к упариванию. Показана динамика изменения концентрации урана и радиационной активности технологических растворов. Представлены результаты сравнительного анализа эффективности перемешивания в емкостях приема с существующими перемешивающими устройствами и с предложенными модернизированными системами перемешивания.

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Nitric acid uranium solutions chemical composition and radiation activity averaging processes intensification

Khomjakov A., Ph. D., Mordanov S., Nikulin V., Ph. D. (FSAEI HPE Ural Federal University named after the first President of Russia B.N.Yeltsin – UrFU) Korchenkin K., Ph. D., Melent’ev A., Ph. D. (FSUE Mayak PA).

The researches results of the chemical nitric acid uranium solutions chemical composition and radiation activity averaging processes in the reception tanks during the preparation for evaporation are presented. The dynamics of uranium concentration and radiation activity alteration of technological solutions is shown. The comparative analysis results of mixing efficiency in the reception tanks via existing mixing equipment and offered modernized mixing systems are presented.

А.М. Киркин, А.В. Курындин к.т.н., А.А. Строганов, к.ф.-м.н., И.А. Ляшко, М.Ю. Карякин ФБУ «НТЦ ЯРБ», г. Москва, kirkin@secnrs.ru.
По материалам 18-ого Международного симпозиума по упаковке и транспортировке радиоактивных материалов (PATRAM-2016), прошедшего в Японии (г. Кобе) с 18 по 23 сентября 2016 года.

Представлен доклад, посвященный вопросам независимой оценки параметров безопасности, как неотъемлемой и необходимой части экспертизы обоснований безопасности ядерных установок и деятельности в области использования атомной энергии. Отмечено, что такие независимые оценки способствуют повышению качества экспертизы безопасности и в конечном итоге приводят к повышению уровня безопасности. Кроме того, в докладе указано, что качество независимых оценок параметров безопасности, осуществляемых организациями научно-технической поддержки регулирующих органов безопасности должно быть подтверждено расчетными и/или экспериментальными исследованиями оцениваемых параметров.

В докладе описаны используемые в ФБУ «НТЦ ЯРБ» расчетные и экспериментальные методы оценки параметров безопасности при транспортировании отработавшего ядерного топлива в транспортных упаковочных комплектах (на примере ТУК-153). Приведен обзор экспериментальных установок, используемых для верификации расчетных моделей, перечень допущений и приближений, используемых в расчетных моделях, а также результаты сравнения расчетных значений параметров безопасности со значениями, полученными экспериментальным путем. В конечном итоге выполнена верификация используемых в ФБУ «НТЦ ЯРБ» расчетных моделей для независимой оценки параметров безопасности при транспортировании ОЯТ и подтверждена их консервативность.

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The TSOF Consultancy Meeting on developing technical and scientific capabilities of TSOs supporting regulatory functions in embarking countries took place at IAEA HQ in Vienna on 4-6 July, 2016.

TSO Forum Consultancy Meeting to develop an action related to the capacity building of technical and scientific organisation of embarking countries was held at IAEA Headquarters in Vienna (Austria) on 4-6 July, 2016.

As a follow-up of the TSO Conference in Beijing, the TSOF Steering Committee decided in March 2016 to develop an action related to the capacity building of technical and scientific organisation of embarking countries.

As a first step a consultancy meeting was arranged by IAEA with the objective to share the experience and discuss among the experts from TSOF-members on their experiences with embarking countries needs in the field of TSO capability, review existing IAEA documents, missions and tools linked to TSO capabilities and provide recommendations for future steps.

Besides representatives of CNSC (Canada), NRC (USA), JRC (EC), TSC/VARANS (Vietnam) and IAEA the meeting was attended by the experts of ETSON members – GRS (Germany), VTT (Finland), IRSN (France), SEC NRS (Russia) and ENSTTI.

The experts presented their experience feedback in peer review missions and expert missions developed by IAEA (such as INIR, IRRS and other experts mission in capacity building) and other peer reviews and their experience feedback in developing support to TSOs for regulatory bodies of embarking countries. They developed proposals addressing the support of the technical and scientific capacity of TSOs in embarking countries and further steps for TSOF on related issues.

Contact

Denis Mistryugov, SEC NRS, mistryugov@secnrs.ru.

Source

www.eurosafe-forum.org/node/274

The physical start-up of the world’s first power unit of Gen III+ took place this May at Novovoronezh NPP. The appropriate license was issued by the Federal Environmental, Industrial and Nuclear Supervision Service (Rostechnadzor) taking into account the safety review performed by SEC NRS.

On March 22, 2016 Rostechnadzor granted Concern Rosenergoatom JSC (Russian utility) with license to operate nuclear installation of Unit No.1 of Novovoronezh NPP-2 (NVNPP-2).

The physical start-up of this power unit took place on May 20, 2016; it was constructed under the «AES-2006» design (VVER-1200) and belongs to new Generation III+ type reactors. Application of additional safety systems together with active regular ones is the specifics of this reactor type. The availability of such systems suggests the qualitatively new safety level of reactor, which design solutions incorporated the Fukushima-Daiichi NPP accident lessons learnt.

As established by the licensing procedure, Rostechnadzor decides to grant the license or to refuse granting taking into account the expert conclusions on safety of NPP operation that are prepared by the technical and scientific support organization – SEC NRS.

In the course of safety review in respect to Unit No.1 of NVNPP-2, SEC NRS carried out assessment of Safety Analysis Report (18 chapters), NPP unit technological procedures, design basis accident management guideline, BDBAs management guideline, QAP, NPP unit commissioning programms and other documents prescribed by the requirements in force. Almost 100 specialists in various scientific and technical areas were involved in the safety review which had been carried out for nearly two years. Issues raised in the frames of the submitted documentation review as well as  Rostechnadzor inspections were also subject to discussions with the operating organization.

Contact

Denis Mistryugov, SEC NRS, mistryugov@secnrs.ru.

Source

www.eurosafe-forum.org/node/273.

The International workshop “Treatment processes for the sustainable management of radioactive waste including innovative techniques” organized by the ETSON WM&D Working Group in collaboration with IAEA took place in the IAEA premises in Vienna within the period from the 4th to 6th of July 2016.

About 20 representatives of CEA (France), KIT (Germany), IAEA and ETSON members participated in the workshop.

The workshop objective was to summarize, present and analyze the information for different radioactive waste types from the various radioactive waste generating industries and activities. Aspects which could benefit from future collaboration such as joint research, harmonization of safety demonstration approaches or review and development of safety standards were identified.

These outcomes will be taken back to the ETSON WM&D WG for further consideration and will also be presented and discussed at the forthcoming IAEA Conference on the safety of radioactive waste management scheduled which will take place in November 2016 in Vienna.

Contact

François Besnus, IRSN, francois.besnus@irsn.fr.

Alexey Plevaka, SEC NRS, plevaka@secnrs.ru.

Source

www.eurosafe-forum.org/node/275.

Federal Environmental, Industrial and Nuclear Supervision Service (Rostechnadzor) and Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) took part in the VIIIth International Forum «ATOMEXPO 2016», the X International Scientific and Technical Conference on Safety, Efficiency and Economics of Nuclear Power Industry (MNTK-2016) and the VII International Conference and Exhibition «ATOMEXPO BELARUS 2016» hosted in Moscow and Minsk between April and June 2016.

International specialized exhibition and a congress with the involvement of representatives from international, national and public organizations, Russian and foreign companies, core experts in the nuclear power industry was organized at the «ATOMEXPO 2016» International Forum in Moscow, Russia in June, 2016.

«Nuclear Power as a Basis for Zero Carbon Energy Balance» was the main topic of the Forum. The Forum gave nuclear power industry world leaders an opportunity to analyze and discuss contemporary challenges faced by the energy market, to determine nuclear power industry perspectives as the pillar for sustainable social and economic development of countries.

Congress under the frames of the Forum featured the following:

• Round table «Fuel Supply and Back End – Integrated Solutions. Competitiveness and Environmental Acceptability of Nuclear Energy Now and in the Future»;
• Round table «Creation of Nuclear Science and Technology Centers. Rosatom State Corporation’s International Scientific Cooperation Projects Illustrated by the MBIR Project»;
• Round table «Lifecycle Management. From NPP Construction Management to NPP Information Management Throughout the Lifecycle»;
• Round table «Internal Control in Company Management System»;
• Plenary session «Nuclear Power as a Basis for Zero Carbon Energy Balance»;
• Round table «Energy Balance Optimization, Environmental and Economic Aspects. Nuclear and Renewable Energy»;
• Plenary session «Future of Nuclear Power. New Players»;
• Business-dialogue «Nuclear fuel supply safety and unique technologies – basis for NPP fuel supply partnership development (20 years of successful cooperation)»;
• Round table «Countries on the Threshold of Nuclear Development: Global Challenges and Solutions by Rosatom»;
• Round table «Creation of Nuclear Science and Technology Centers on research reactor basis. Business and scientific application»;
• Round table «Innovative Products for Sustainable Development»;
• Round table «Eco-efficient Technologies of Nuclear Industry: Today and Tomorrow»;
• Round table «Legal Issues of NPP Construction Project Financing»;
• Round table «Public Acceptance of Nuclear Technologies and the Rosatom Education Mission».

Forum «ATOMEXPO 2016» has attracted more than 5 000 persons from 55 countries. The exhibition event held within the Forum was attended by 99 Russian and foreign companies.

The participation in congress has allowed:

• the world leaders of the industry to exchange advanced practices and experiences to implement new approaches;
• to contribute to the dialogue with government structures, expert, scientific and business communities regarding the world nuclear power development issues;
• to get a clear picture about the needs and the possibilities of nuclear power industry;
• to highlight their progress achieved in nuclear power industry;
• to increase considerably their contacts, to present products and services to the representatives of the world nuclear power industry.

The MNTK-2016 Conference (Moscow, May, 2016) has provided an opportunity to share experience and information on key issues of NPP operation and perspectives for nuclear power development; this event has facilitated the decision-making in respect to the following urgent issues:

• ensuring the priority of NPP operation safety;
• improving the economic efficiency of power units operation;
• extension of power units operation period;
• SNF and RW management; provisions for decommissioning of NPP units;
• nuclear power engineering development through construction and commissioning of new generation units, development and implementation of promising designs.

In addition to the plenary sessions, the Conference included sessions of the following sections:

• «Safe and efficient operation of Russian NPPs»;
• «Nuclear power development»;
• «Nuclear power economics»;
• «International cooperation focused on ensuring NPPs safety»;
• «Human resource for the nuclear power».

The following topical areas were addressed in the course of sections sessions:

• Operation, maintenance and repair of NPPs with VVER, RBMK, BN and EGP reactors;
• Engineering support to NPP operation;
• Radiation safety, NPP ecology, emergency preparedness;
• Nuclear power economics;
• Development of new nuclear power units;
• Advanced nuclear power projects;
• International cooperation focused on ensuring NPPs safety;
• Training of young specialists for NPPs and transfer of veterans’ experience.

The exhibition organized as part of MNTK-2016 included exhibits presented by the leading Russian enterprises of the industry and foreigners attended the Conference.

The main objectives of ATOMEXPO – BELARUS 2016 Exhibition and Conference were the demonstration of the novel technologies available in design, construction, operation and safety ensuring of an NPP; provision for efficient equipment supply chains needed for Belarus NPP construction; facilitating the system formation on nuclear power industry personnel training in the Republic of Belarus.

Research and practice conference «The Development of the Nuclear Power Industry in the Republic of Belarus» was organized in the frames of Forums business program and it included a plenary session, round table meetings and presentations by exhibiting companies.

The principle topics of this Conference were:

• «Construction of the Belarus NPP; building works and equipment supply»,
• «Nuclear Power Infrastructure Development in the Republic of Belarus» and
• «Public Acceptance of Nuclear Power».

More than 70 organisations and companies from Russia and the Republic of Belarus were presented at «ATOMEXPO – BELARUS 2016». The Exhibition and the Conference brought together the representatives from leading Russian and Belorussian enterprises providing works and services to nuclear power industry. More than 600 specialists from Russia, the Republic of Belarus and the European countries took part in the business program.

In the frames of the Exhibition new technologies and equipment were demonstrated as well as the best innovations and pressing industry-specific issues were addressed, prospects for development were emerging and partnership relations were building a chain.

During exhibitions and forums the exhibitors stands of SEC NRS presented the information to the full extent showing the activities under implementation for scientific and technical support to nuclear and radiation safety regulation including analysis and substantiation of criteria and safety requirements at the use of atomic energy.

Contact

Andrey Balalaechnikov, SEC NRS, balalaechnikov@secnrs.ru.

Source

www.eurosafe-forum.org/node/276.

Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) is ETSON Associated Member since 2012. It is a non-profit organization providing full-fledged technical and scientific support to Rostechnadzor.

Status of SEC NRS

SEC NRS is a non-profit organization, Federal Budget Enterprise and of Federal property. SEC NRS with the authorized staff size of 350 people provides full-fledged scientific and technical support to Rostechnadzor.

Roles and duties of SEC NRS

Drafting regulations in the field of nuclear and radiation safety is one of the high-priority activities of SEC NRS. Its systematic updating and harmonization with international safety standards is provided by SEC NRS experts with the involvement of broad spectrum of Rostechnadzor and other competent authorities’ specialists.

SEC NRS is entrusted to perform safety review of nuclear facilities and/or types of activities within Rostechnadzor licensing procedure. The top-level experts are participating in such review realization.

SEC NRS R&D works are the scientific basis for all others types of activities aimed at scientific and technical support.

R&D Activities of SEC NRS

• Neutron and nuclear physics;
• Integrity and reliability of reactor, pipelines and facility equipment;
• Methods, models and calculations for design and beyond design basis accidents, accident consequences including analysis of radioactive products and radioactive releases propagation to the environment;
• Probabilistic and deterministic safety assessment;
• Control, account and physical protection of nuclear materials;
• Stability and reliability of buildings, structures and constructions to external impacts;
• Safety of nuclear materials, spent nuclear fuel, radiation sources and radioactive waste management at different phases, including aspects of long-term safety;
• Analytical and information support to Technical Emergency Center of Rostechnadzor (Crisis center).

SEC NRS is also involved into training of inspectors and its personnel. The Centre organizes conferences and workshops, updates the necessary databases, publishes and distributes regulatory documents of Rostechnadzor. SEC NRS publishes “Nuclear and Radiation Safety” journal, which is an official journal of Rostechnadzor.

All works performed by SEC NRS are based on sharp examination of national and international experience of nuclear facilities designing, operation, the accumulated and state-of-art level of science and technology, approaches of review and safety supervision realization.

Activity of SEC NRS is in close interaction with “Rosatom” State Corporation organizations and its structural subdivisions in implementation of the Federal Target Programs, international cooperation, public relations and economic contracts, etc.

International Cooperation

SEC NRS implements a very strong partnership with foreign TSOs and participates in the work of Committees, Commissions and Working Groups of the following international organizations:

• IAEA;
• Technical and Scientific Support Organizations Forum (TSOF). SEC NRS was nominated by Rostechnadzor as a representative of Russia to the Steering Committee of TSO Forum;
• Nuclear Energy Agency of the Organization for Economic Cooperation and Development (NEA/OECD);
• Forum of the State Nuclear Authorities of the countries operating WWER Reactors;
• Western European Nuclear Regulators Association (WENRA);
• European Technical Safety Organizations Network (ETSON). SEC NRS is a member of ETSON since June 2012;
• TSOs and organizations from CIS, Western Europe, Central and Eastern Europe, Asia, America.

SEC NRS provides scientific and technical assistance to regulatory authorities of countries embarking on nuclear power program (Vietnam, the Republic of Belarus, Turkey, Bangladesh, Jordan and others). SEC NRS renders different types of services to its foreign partners, including support in the development of national regulatory infrastructure and regulatory and legislative framework, scientific and technical consulting of the regulator’s activity and joint realization of expert reviews.

SEC NRS strengthens interactions with traditional and regular partners from countries operating reactors of the Russian design. SEC NRS specialists are involved into Forum of the State Nuclear Authorities of the Countries, Operating WWER Type Reactors to discuss current state of safety level and progress of interaction in order to improve nuclear and radiation safety in the Russian Federation and worldwide.

Contact

Denis Mistryugov, SEC NRS, mistryugov@secnrs.ru.

SEC NRS

Russia, 107140, Moscow, Malaya Krasnoselskaya st. 2/8, bld. 5;
Phone: +7 (499) 264-00-03;
Fax: +7 (499) 264-28-59;
E-mail: secnrs@secnrs.ru.

For more information visit SEC NRS web-page: http://www.secnrs.ru/en/.

Source

www.eurosafe-forum.org/node/277.

Букринский А.М., к.т.н., Ланкин М.Ю., к.т.н., Шарафутдинов Р.Б., к.т.н. (ФБУ «НТЦ ЯРБ»), Мирошниченко М.И. (Ростехнадзор), Сидоренко В.А., д.т.н., проф., чл.-корр. РАН (НИЦ «Курчатовский институт»).

Изложены основные отличия вновь введенных «Общих положений обеспечения безопасности атомных станций» (НП-001-15) от ранее действовавших федеральных норм и правил «Общие положения обеспечения безопасности атомных станций» ОПБ-88/97.

Полную версию статьи можно скачать по ссылке.

The updated general regulations on ensuring safety of nuclear power plants were put into effect

Bukrinsky A., Ph.D., Lankin M., Ph.D., Sharafoutdinov R., Ph.D. (SEC NRS), Miroshnichenko M. (Rosteсhnadzor), Sidorenko V., professor, Corresponding Member of RAS (Kurchatov Institute).

The paper presents main differences between the newly introduced “General regulations on ensuring safety of nuclear power plants” NP-001-15 and previously effective “General regulations on ensuring safety of nuclear power plants” OPB-88/97.

Соколов И.П., д.х.н. (ФБУ «НТЦ ЯРБ»).

Определены зависимости температуры самовоспламенения пирофорного материала от размера его частиц, соотношения реагентов, давления в системе.

Скачать статью целиком можно в формате PDF.

Physical-chemical conditions of pyrophoric materials auto-ignition

Sokolov I., Ph.D. (SEC NRS).

Auto-ignition  temperature  functions  of  particles  size,  relation  between  reagents,  system  pressure  are suggested.

Былкин Б.К. (НИЦ «Курчатовский институт»), Чуйко Д.В., Тихоновский В.Л. (АО «НЕОЛАНТ»).

На опасных производственных объектах, таких как атомные электростанции и другие организа- ции атомной отрасли, нештатное развитие ситуации при выполнении ряда технологических операций, например, при демонтаже графитовой кладки реактора, чревато не только дополнительными финан- совыми и временными затратами на выполнение корректирующих действий, но и негативным воздей- ствием на персонал и окружающую среду. В связи с этим очень важно предварительно осуществлять верификацию сложных технологических процессов, особенно таких, которые будут выполнены впервые на данном предприятии и/или в отрасли/мире в целом.

Статью целиком можно скачать в формате PDF.

Interactive simulation 3d model as a tool supporting personnel radiation safety at decommissioning activities

Bylkin B. (NRC «Kurchatov Institute»), Chuiko D., Tikhonovsky V. (NEOLANT JSC).

Abnormal incident evolution on dangerous industrial facilities like nuclear power plants and other nuclear facilities at some process procedures, such as dismantling reactor graphite stack, threatens not only with extra financial and time expenditures for mitigating measures, but also with negative effect on the personnel and environment. Therefore preliminary verification is essential for sophisticated process procedures, especially if they will be carried out for the first time at the plant and/or the industrial brunch/in the world.

Линге И.И., д.т.н., Дорогов В.И., к.ф.-м.н. (ИБРАЭ РАН), Шарафутдинов Р.Б., к.т.н., Непейпиво М.А. (ФБУ «НТЦ ЯРБ»), Хаперская А.В., к.х.н. (Госкорпорация «Росатом»).

В статье приводится краткий анализ опыта представления национальных докладов Российской Федерации по выполнению обязательств, вытекающих из Объединенной конвенции о безопасности обра- щения с отработавшим топливом и о безопасности обращения с радиоактивными отходами, на совеща- ниях договаривающихся сторон за период 2006 – 2015 гг.

Статью целиком вы можете скачать в формате PDF.

About experience of presenting of national reports of the Russian Federation to fulfill the obligations under the Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

Linge I., Dr., Dorogov V., Ph.D. (IBRAE RAN), Sharafoutdinov R., Ph.D., Nepeipivo М. (SEC NRS), Khaperskaya А., Ph.D. (Rosatom).

The article provides a brief analysis of the experience of presenting of national reports of the Russian Federation to fulfill the obligations arising from the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management at the Review meetings of the Contracting parties during the period 2006 – 2015.

Хамаза А.А., Бочкарев В.В., Курындин А.В., к.т.н., Абакумова А.С. (ФБУ «НТЦ ЯРБ»), Тихомиров Г.В., д.ф-м.н. (НИЯУ «МИФИ»).

В статье рассмотрены особенности применения риск-ориентированного подхода при регулировании безопасности объектов «ядерного наследия». На примере пунктов размещения и пунктов консервации особых РАО продемонстрирована возможность использования комплексного показателя потенциальной опасности объектов «ядерного наследия» в качестве одного из основных факторов риска.

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Concerning the possibility of applying the safety and environmental detriment score as the basis of the differential approach to the safety regulation of
«nuclear legacy» facilities

Khamaza A., Bochkarev V., Kuryndin A., Ph.D., Abakumova A. (SEC NRS), Tihomirov G., Ph.D. (MEPhI).

This paper considers the particularities of application of the risk-informed approach for the safety regulation of «nuclear legacy» facilities. The possibility of applying the safety and environmental detriment score in the capacity of one of the main risk factors is demonstrated by the example of special radioactive waste emplacement facilities and special radioactive waste isolation facilities.

Хамаза А.А. (ФБУ «НТЦ ЯРБ»).

В статье представлены предложения по внедрению риск-ориентированного подхода в контрольно- надзорной деятельности в области использования атомной энергии с поэтапным переходом от стати- ческой к динамической модели оценки риска.

Полную версию статьи вы можете скачать в формате PDF.

Proposals on the implementation of risk-informed approach for control and supervision in the field of use of atomic energy

Khamaza A. (SEC NRS).

This paper presents the proposals on the implementation of risk-informed approach for control and supervision in the field of use of atomic energy by the means of step by step transition from static to the dynamic system of risk assessment.