T. Okuda, Hideki Takahashi, Tomoyoshi Watakabe, M. Morishita
{"title":"Effect of the Plasticity of Piping and Support Structures on the Seismic Response of Piping Systems","authors":"T. Okuda, Hideki Takahashi, Tomoyoshi Watakabe, M. Morishita","doi":"10.1115/icone29-89097","DOIUrl":"https://doi.org/10.1115/icone29-89097","url":null,"abstract":"\u0000 This study describes the results of seismic analyses conducted to clarify the effect of the plastic deformation of a pipe and its support structures on the seismic response of the entire piping system. The first type of analyses includes the investigation of plasticity with regard to the following parameters: (1) none, (2) piping, (3) support structure, and (4) piping and support structure. The second type of analyses includes the parametric survey of the yield load and post-yield stiffness of the restoring force characteristics of support structures.\u0000 The results of the first type of analyses have demonstrated significant implications on the seismic design of piping systems based on the elastic-plastic response analysis. First, the piping response, i.e., elbow strain, is significantly reduced when plasticity is considered in the piping support. On the contrary, the piping support response is not so much affected by the piping plasticity.\u0000 The results of the second type of analyses showed that the yield load of the support structure significantly affects the response of the piping system, whereas the post-yield stiffness does not affect much compared with the yield load.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"41 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128085725","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}
Rui Wang, Kechen Xu, Kehao Zeng, Hongmei Yan, Wei Bai
{"title":"Analysis of Water Consumption in Nuclear Power Plants and National Standard Formulation for Norm of Water Intake","authors":"Rui Wang, Kechen Xu, Kehao Zeng, Hongmei Yan, Wei Bai","doi":"10.1115/icone29-92414","DOIUrl":"https://doi.org/10.1115/icone29-92414","url":null,"abstract":"\u0000 The nuclear power industry consumes a large amount of water. Its water process systems are complex, and require high water guarantee rate. In general, water process and water consumption indexes for different nuclear power plants are still in the exploratory stage. For a long time, there are huge differences between the design values and actual values of water intake, water consumption, and water withdrawal in China nuclear power industry, which brings difficulties to the management. At present, the construction of nuclear power plants in China is in a period of rapid development, but there is no national standard for norm of water intake, yet. Nearly all the design water consumption indexes of nuclear power plants are based on the design values of nuclear power plants that have been built and part water consumption indexes required by few relevant design specifications. With the implementation of the strictest water resources management system, total volume control and norm management have become important tools of water resources management. The national standard formulation for norm of water intake in China’s nuclear power industry can provide a basis for the approval of water intake permits for design and construction of the nuclear power plants, to strengthen the management of water resource and improve the water utilization efficiency of the nuclear power plants. This paper introduces the current situation of water consumption in each nuclear power plant and the basis for national standard formulating for norm of water intake.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"79 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126313150","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}
Fangqiang Chen, Yang Zhang, Wei Jia, Zhaotong Li, Guanyi Wang
{"title":"Research on the Practice Qualification System of Registered Nuclear Safety Engineer From the Perspective of Access Professional Qualification","authors":"Fangqiang Chen, Yang Zhang, Wei Jia, Zhaotong Li, Guanyi Wang","doi":"10.1115/icone29-92500","DOIUrl":"https://doi.org/10.1115/icone29-92500","url":null,"abstract":"\u0000 In order to improve the professional and technical level of China’s nuclear and radiation safety practitioners, enhance their safety literacy, China established Registered Nuclear Safety Engineer Qualification License System (hereinafter referred to as RNSES). Registered nuclear safety engineers not only need to master the knowledge of nuclear safety professional technology, but also need to master the knowledge of nuclear safety laws and regulations, department rules, nuclear safety guidelines, relevant national standards and industry standards, nuclear safety culture, etc. RNSES has good advantages and positive support for the implementation of nuclear safety regulations and national standards in the nuclear field. Nevertheless, the system has been established for 20 years and has accumulated some problems to be solved. Now, RNSES is planned to be adjusted. From the perspective of professional qualification of admittance, the paper makes a multi-dimensional statistical study on the construction of other professional qualification access systems, intuitively points out the realities and shortcomings of the registered nuclear safety engineer system, and then puts forward specific suggestions to strengthen the construction of the access system of certified nuclear safety engineers, so as to provide policy reference for the system reform.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126668104","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}
Shangyuan Liu, R. Wei, Shao-hua Zhang, Feifei Wu, Jianren Du
{"title":"Comparative Analysis and Research on Nuclear Power Regulation & Standard System and Standardization Works Among China, the U.S. and Japan","authors":"Shangyuan Liu, R. Wei, Shao-hua Zhang, Feifei Wu, Jianren Du","doi":"10.1115/icone29-93642","DOIUrl":"https://doi.org/10.1115/icone29-93642","url":null,"abstract":"\u0000 As the world’s leading countries in nuclear power fields, China, the United States, and Japan have relatively sound nuclear power regulation and standard systems. The nuclear power standardization works have also been gradually improved and optimized with the iteration of good practices and the feedback of best experience. Nevertheless, it couldn’t be denied that the paths followed by these countries are not exactly same, due to diversities of state institutions and mechanisms, as well as inherently different national politics, history, technology, and culture. Making periodical revisions on development approach, each country establishes unique, well-applicable, self-consistent system framework and operating model.\u0000 With a systematic review, this paper will summarize the current R&D of the countries’ nuclear power regulation & standard system, as well as the latest states on the development of standardization works on both domestic and abroad scales, following by some fruitful comparative analyses. Using the literature research method and Differentiation Competitive Strategy methodology, this paper will also critically analysis advantages and shortcomings respectively, which would be helpful to understand the regulation and system operations comprehensively and objectively, for each country. Additionally, inspirations would be brought to seek an opportunity deepening extensive collaborations for the forthcoming nuclear power international standardization works. This paper will make comments and put forward suggestions focusing on strengthening R&D cooperation among multilateral countries. Ultimately, to improve the diversification and interoperability of nuclear emerging technologies and industrial chain, also accelerate global promotion and common prosperity, via the nuclear field standardization approach.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"60 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130753004","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":"Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels","authors":"Jun Pan, Chang Liu, Xihui Su","doi":"10.1115/icone29-93037","DOIUrl":"https://doi.org/10.1115/icone29-93037","url":null,"abstract":"\u0000 ASME Code Section XI IWB-3500 gives the acceptance standards for in-service inspection of reactor pressure vessels, according to which the acceptable ratios of depth-to-thickness (a/t) varies along with depth-to-length ratios (a/l) for defects detected by nondestructive examination of reactor pressure vessels during the in-service stage. The acceptance standards are established based on fracture mechanics and five principal safety criteria as per EPRI NP-1406-SR, among which the safety margin between “allowable indication” in ASME Code Section XI and maximum postulated defects meeting ASME Code Section III fracture mechanics requirements is of most concern. The establishment of the acceptance standards can facilitate the development of new allowable indication standards to determine the component’s adequacy for continued service.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"17 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"125242538","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}
Chen Yuxiu, Wang Yuhong, Luo Haiying, Wang Jinkai, Shi Qing, Zhu Zengpei, Wu Bei
{"title":"Discussion on Selection of Codes and Standards on Nuclear Power Plant Safety","authors":"Chen Yuxiu, Wang Yuhong, Luo Haiying, Wang Jinkai, Shi Qing, Zhu Zengpei, Wu Bei","doi":"10.1115/icone29-92615","DOIUrl":"https://doi.org/10.1115/icone29-92615","url":null,"abstract":"\u0000 Requirements of evaluating and determining applicability, adequacy and sufficiency of codes and standards applied in nuclear power plant design are required by IAEA, NNSA etc. without detailed guidance or suggestion yet. Purpose of the article is going to discuss and provide a methodology for selecting codes and standards methodology to evaluate their applicability, adequacy and sufficiency, purpose is tying to react those requirements. The methodology is explored based on GDA (Generic Design Assessment) practice, 5 steps are included: breakdown of design activities, collection and identification, evaluating applicability and adequacy, evaluating sufficiency, evaluating consistency. Process and detailed evaluation method are discussed. Selection process could supplement the gap of selecting applicable codes and standards, providing a mentality for engineers to focus on and continually raising other better process or methods for ensuring applicable codes and standards can be selected at the beginning of the nuclear power plant design and implementing nuclear security culture more deeply on selection of codes and standards.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"47 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129563514","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":"Establishment of Engineering Economics Standard System for Nuclear Power Plants in China","authors":"Wen Yang, S. Zhang, Jun Huang, Feifei Wu","doi":"10.1115/icone29-90525","DOIUrl":"https://doi.org/10.1115/icone29-90525","url":null,"abstract":"\u0000 Standard system has been developed for Nuclear Power Plants in China during the last ten years, which covers the entire lifespan of pressurized water reactors. It is mainly composed of the following parts, including general & foundation, preliminary work, designing, equipment, construction, commissioning, operation and decommissioning. Engineering economics is an important part of general & foundation section. Standards related to cost and cost management constitute engineering economics standard system, which is one of the most important subsystems in the standard system for Chinese nuclear power plants. In general, engineering economics standard system is composed of 39 nuclear industry standards, with 4 management standards, 6 specifications of bill of quantities and 29 cost quota standards.\u0000 Management standard specifies the engineering management and engineering cost evaluation for the construction of nuclear power plants. For the technical part of engineering economics standard system, two kinds of pricing methods for construction projects in china should be considered: fixed quota pricing and bill of quantities, and those standards should cover the overall construction content and construction phase of nuclear power plants.\u0000 This paper presents the establishment of engineering economics standard system framework and major elements in this system. The study in this paper shows a good example of the establishment of the standard system in engineering economics field for nuclear power plants in China.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129019893","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}
Feng Lv, Zhengyu Zhou, Zhilin Chen, Han Liu, Zihao Zheng
{"title":"A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients","authors":"Feng Lv, Zhengyu Zhou, Zhilin Chen, Han Liu, Zihao Zheng","doi":"10.1115/icone29-94327","DOIUrl":"https://doi.org/10.1115/icone29-94327","url":null,"abstract":"\u0000 Mechanical components of nuclear power plant are subject to variations in temperature and pressure, which cause stress and ultimately induce fatigue damage. Usually, these variations, called operational transients, are well identified through the use of sensors and can be easily classified into design transients and associated to different reactor states and functional situations. However, a number of operational transients cannot be covered by the corresponding design transients due to temperature or pressure parameters exceeding the defined surveillance thresholds. In that case, an alternative is to find a more severe design transient to cover the operational transient, and then justify the existing design fatigue analysis remain valid. This process is today not existent in design standards and partially mentioned in standards such as RSE-M, yet it is critical for the safe operation of plants especially in the domain of Long Term Operation (LTO). In this paper, a set of mechanical criteria is developed to compare the severity between transients, which include four aspects: maximum stress state, minimum stress state, alternating stress intensity and fatigue damage. A three-dimensional rain flow method is used to identify extreme stress state and to detect multiaxial stress peak and valley. As an example, a typical nozzle is assumed to endure a non-classified operational transient. The envelope analysis for this transient classification is demonstrated and a design transient is selected to cover the operational transient. The numerical simulation results show that if a design transient and an operational transient satisfy the mechanical criteria strictly, then the operational transient can be bounded by the design transient. The proposed mechanical criteria are consistent with the requirements of the RCCM and RSE-M codes in term of preventing fatigue damage.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"110 2 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"122616990","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}
Feifei Wu, Zhenbang Dong, Jun Huang, Shangyuan Liu
{"title":"Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment","authors":"Feifei Wu, Zhenbang Dong, Jun Huang, Shangyuan Liu","doi":"10.1115/icone29-93746","DOIUrl":"https://doi.org/10.1115/icone29-93746","url":null,"abstract":"\u0000 The development of nuclear power safety and the global procurement of nuclear power equipment have put forward an urgent need for the integration of nuclear power standards. In this paper, the development history and technical status of the localization of pressure equipment in China’s PWR nuclear power plants is introduced. This paper expounds the technology innovation and engineering experience of China’s independently-developed third-generation PWR nuclear power based on “HPR 1000” and “CAP 1400”, and the main goals, principles and basic ideas of the integration of technical standards for nuclear pressure equipment by sorting out and analyzing the list of topics in the fields of materials, design, manufacturing, welding, non-destructive testing and other professional fields involved in the integration of China’s nuclear pressure equipment standards, comparing with the technical topics involved in the current work of the SDO Integration Committee, and further discussing the differences and connections. This paper discusses the future development trend of nuclear pressure equipment in pressurized water reactor nuclear power plants and the demand for standardization of key technologies, and proposes the main problems that should be paid attention to and solved in the next step in the integration of nuclear pressure equipment standards.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"87 3 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130678305","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":"The Drafting and Discussion of Terminology of Aging and Life Management for Nuclear Power Plant in China","authors":"Zhiming Zhong","doi":"10.1115/icone29-90645","DOIUrl":"https://doi.org/10.1115/icone29-90645","url":null,"abstract":"\u0000 From 2016, we started to draft the industry standard of “Terminology of aging and life management for nuclear power plant “(NB/T 200555-2019)”. After three years, it was issued in China and came into recommend implementation at July, 2020. As ageing management and life management activities are important part of periodic safety review or operating license renewal for nuclear power plants, the standardization of ageing management and life management terms and terminology will benefit the related practice, technical communication and international cooperation. This paper briefly introduced the drafting background, aims, principals, methodology, and process of this industry standard in China. The standard’s scope, structure and terms category were discussed and analyzed briefly also. Then the difference between it and EPRI “Nuclear Power Plant Common Aging Terminology” (TR-100844) was discussed. After that, polishing the definitions of some essential terms was introduced in detail. Some of drafting experience was discussed also. In final, the issued standard includes 124 terms, which be classified into five categories as basic concept, aging mechanism, aging effects, aging management and life management. We believed that it will contribute the standardization and application of relevant terminology and benefit international communication in nuclear power plant aging and life management area.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"26 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123630251","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}