Nuclear and Radiation Safety最新文献

{"title":"Additional references","authors":"Andrew Cooper","doi":"10.1016/b978-0-12-818326-7.00034-2","DOIUrl":"https://doi.org/10.1016/b978-0-12-818326-7.00034-2","url":null,"abstract":"","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":"51 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91129332","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Scenarios and Pathways of Radionuclide Releases from Near-Surface Waste Disposal Facilities: A Brief Overview of Historical Evidence","authors":"D. Bugai, R. Avila","doi":"10.32918/nrs.2020.3(87).03","DOIUrl":"https://doi.org/10.32918/nrs.2020.3(87).03","url":null,"abstract":"The very low-level waste (VLLW) produced during decommissioning of nuclear facilities can be suitable for disposal in landfill type facilities. Considering the similarities in design, the experience gained in near-surface disposal of radioactive waste in trenches and vaults is relevant to the issue of VLLW disposal in landfills. This paper presents a brief review of internationally reported cases of radionuclide releases from near-surface disposal facilities. Based on this review, the conclusions are made that the following radionuclide release and exposure scenarios should be accounted for in safety assessment of VLLW disposal in landfills: i) leaching from waste to groundwater by atmospheric precipitations; ii) bath-tubing scenario; iii) scenarios caused by extreme meteorological and hydrological events (erosion, flooding, etc.); iv) human intrusion. The gaseous transport deserves attention for a number of relevant radionuclides, such as (C-14, Rn-222, etc.). In addition, the possibility of early degradation of engineered containment structures (soil covers, bottom seals) should be cautiously considered.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46820132","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Results of Analysis of Aging Related Events at Ukrainian NPPs","authors":"O. Shugailo, O. Ligotskyy, O. Pecherytsia, O. Kulman, R. Moskalyshyn, R. Khalenko, O. Kurman","doi":"10.32918/nrs.2020.2(86).06","DOIUrl":"https://doi.org/10.32918/nrs.2020.2(86).06","url":null,"abstract":"The design lifetime (30 years) of Ukrainian NPPs has already been expired or will be expired soon. One of the priority areas for the development of nuclear energy is long-term operation (LTO) based on the results of periodic safety review. At present, eleven Ukrainian NPP units are operated under LTO conditions, which in turn causes certain features of operation related to wear, fatigue and general aging of components and structures. \u0000An issue of aging management is considered one of the main factors to ensure the safety of a nuclear installation, both in the design lifetime and in the long-term operation. The primary purpose of aging management is to ensure the safety and maximum efficiency of operation through the implementation of technically and economically feasible measures aimed at timely detection and keeping of degradation of NPP components caused by aging within the limits. \u0000One way to determine the efficiency of implemented measures and aging management programs is to analyze operational experience and, in particular, analyze the number of NPP operational occurrences during the design and long-term operation period and that are directly related to the aging effects. This paper presents the results of the analysis of the events at Ukrainian NPPs caused by aging processes, compares the results of national and international experience.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48097300","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Analysis of Processes in the Containment Using ATHLET-CD and COCOSYS Codes","authors":"M. Vyshemirskyi, V. Pustovit, V. Kravchenko, D. Donskyi","doi":"10.32918/nrs.2020.2(86).04","DOIUrl":"https://doi.org/10.32918/nrs.2020.2(86).04","url":null,"abstract":"A brief description of performed input deck modifications and results of stand-alone and coupled calculations of Dn 200 mm loss of coolant accident with simultaneous total station blackout accident scenario for Rivne Nuclear Power Plant Unit 1 (WWER‑440/V-213) with application of \u0000ATHLET-CD 3.1A and COCOSYS 2.4 codes are presented in the paper. \u0000ATHLET-CD stand-alone calculation was performed with constant containment pressure (a time dependent volume with constant pressure and temperature was used as a boundary volume for leakage). Further, mass and energy release and fission products from the primary system obtained during ATHLET‑CD stand-alone calculation were used to perform COCOSYS stand-alone calculation. In addition, coupled ATHLET-CD and COCOSYS calculation was performed. All the computer analyzes were performed until the lower head failure. ATHLET‑CD model was extended with core degradation module (ECORE), which allowed calculation of scenario until reactor pressure vessel failure. \u0000According to the results of comparative analysis, nearly the same behavior of the main parameters in the stand-alone and coupled calculation at an early phase of scenario was obtained. Some small differences occur due to distinction in behavior of water and steam mass flows released through the break and due to existence of heat transfer from the primary system structures to the containment compartments during coupled calculation of transient. As for middle and late phases of the accident, some differences between stand-alone and coupled calculation results for analyzed scenario are present. These differences are caused by different total fission products and aerosols release from the reactor coolant system to the containment compartments. The above information allows recommending application of coupled code/model versions for performing the computer severe accident analyses.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"48767856","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Safety and Reliability Assessment of NPP Instrumentation and Control Systems Considering Different Communication Architectures","authors":"E. Babeshko, O. Illiashenko, V. Kharchenko, E. Ruchkov","doi":"10.32918/nrs.2020.2(86).05","DOIUrl":"https://doi.org/10.32918/nrs.2020.2(86).05","url":null,"abstract":"Safety and reliability assessment of instrumentation and control (I&C) systems used in different safety-critical industries is a responsible and challenging task. Different assessment models recommended by international and national regulatory documents and used by experts worldwide still have disadvantages and limitations. Therefore, studies of assessment model improvements and refinements are essential. This paper proposes that the assessment models be improved by taking into account different architectures of communications both between different systems and within one particular system. In most models, communication lines are considered absolutely reliable, but the analysis performed shows that the communications should be necessarily addressed. Several analytical models are described to assess the reliability of safety-critical systems for nuclear power plants with different communication options.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"45442673","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Application of the FPGA Technology for the Development of Multi-Version Safety-Critical NPP Instrumentation and Control Systems","authors":"A. Perepelitsyn, O. Illiashenko, V. Duzhyi, V. Kharchenko","doi":"10.32918/nrs.2020.2(86).07","DOIUrl":"https://doi.org/10.32918/nrs.2020.2(86).07","url":null,"abstract":"The paper overviews the requirements of international standards on application of diversity in safety-critical NPP instrumentation and control (I&C) systems. The NUREG7007 classification of version redundancy and the method for diversity assessment are described. The paper presents results from the analysis of instruments and design tools for FPGA-based embedded digital devices from leading manufacturers of programmable logics using the Xilinx and Altera (Intel) chips, which are used in NPP I&C systems, as an example. The most effective integrated development environments are analyzed and the results of comparing the functions and capabilities of using the Xilinx and Altera (Intel) tools are described. The analysis of single failures and fault tolerance using diversity in chip designs based on the SRAM technology is presented. The results from assessment of diversity metrics for RadICS platform-based multi-version I&C systems are discussed.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47988393","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Analysis of Safety Aspects of Disused Sealed Radiation Source Disposal","authors":"O. Tokarevskyi, K. Fuzik, S. Kondratiev, Z. Alekseeva","doi":"10.32918/nrs.2020.2(86).09","DOIUrl":"https://doi.org/10.32918/nrs.2020.2(86).09","url":null,"abstract":"Sealed radiation sources (SRS) are extensively used worldwide in agriculture, industry, medicine and different research areas. \u0000If 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. \u0000Since 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. \u0000In 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. \u0000DSRS 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. \u0000DSRS 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. \u0000Current 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. \u0000Solution 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.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"47201694","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Ukrainian NPP Seismic Resistance Assessment Using Provisions of Regulatory Guideline NP 306.2.208-2016","authors":"R. Buryak, D. Ryzhov, O. Horodnichenko, O. Shugaylo, O. Shugailo, M. Mustafin, T. Pidhaietskyi","doi":"10.32918/nrs.2020.2(86).02","DOIUrl":"https://doi.org/10.32918/nrs.2020.2(86).02","url":null,"abstract":"Since November 2016, the new Regulatory Guideline NP 306.2.208-2016 “Requirements for Seismic Resistance Design and for Evaluation of Seismic Safety of Ukrainian NPPs” [1] has been in force in Ukraine. This Guideline was developed to improve requirements for NPP site seismic hazard assessment, NPP seismic resistance design and assessment/review of Ukrainian NPP seismic safety. \u0000Energoatom developed the Organizational and Technical Measures for Implementation of NP 306.2.208-2016 [2] approved by State Nuclear Regulatory Inspectorate of Ukraine to perform NP 306.2.208-2016 [1] requirements. \u0000The paper considers the status of Energoatom in implementation of the main organizational and technical measures [2] on increasing seismic resistance of Ukrainian NPP units according to NP 306.2.208-2016 [1]. In particular, these measures are the following: specification of NPP site seismicity considering results of new studies; introduction of changes into classification (seismic categorization) of systems and components; analysis of necessity to consider additional load combinations with seismic loads, specification of assessing seismic resistance of structures, systems and components; seismic probabilistic safety assessment of NPP units.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":" ","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46563811","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Harmonization of Methodological Approaches and Real Time Radiological Consequence Forecasting Tools","authors":"Yu. Balashevska, Y. Kyrylenko, O. Pecherytsia, I. Shevchenko, V. Bogorad","doi":"10.32918/nrs.2020.2(86).03","DOIUrl":"https://doi.org/10.32918/nrs.2020.2(86).03","url":null,"abstract":"Determination of urgent countermeasures to protect the public in early phase of the accident at NPP requires providing of radiological impact assessment at different distances in real time. These activities involve current meteorological forecast data and information about source term parameters as one of the main part of the emergency сenters functioning worldwide for prompt notification about the radiological or nuclear event in the country, as well as abroad in the case of transboundary impact. \u0000Experts’ background in the assessment and forecasting of radiological consequences area may vary from country to country in terms of methodological approaches, the use of atmospheric dispersion models, doses assessment models, databases, organization procedures, calculation process etc. Possible deviations in the results of assessments performed by experts from different countries may be caused by a number of factors. Their reasons can vary from the use of different information sources to the specifics of protective actions criteria in accordance with national requirements. These factors should be identified both in practice and scientifically. Radiological consequence assessment activities are harmonized at the international level. It is the target of a wide range of international projects. \u0000The paper provides information on modern scientific initiatives aimed at improving assessments and forecasts of radiological consequences to determine urgent countermeasures to protect the public at early phases of an accident at nuclear power plant, in particular, approaches to the initial data preparation and the conduct of assessments and forecasting. A review of international benchmarking activities as well as past emergency exercise overview is presented in the paper. Relevant problems of forecasting radiological consequences in real time are highlighted.","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-06-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43428589","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"When Can We Say That a Particular Plant Is Safe?","authors":"G. Petrangeli","doi":"10.1016/b978-0-12-818326-7.00028-7","DOIUrl":"https://doi.org/10.1016/b978-0-12-818326-7.00028-7","url":null,"abstract":"","PeriodicalId":38519,"journal":{"name":"Nuclear and Radiation Safety","volume":"48 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75637754","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}