scholarly journals PLUTONIUM HANDLING SAFETY ANALYSIS OF THE ROCKY FLATS NUCLEAR SAFETY FACILITY.

1967 ◽  
Author(s):  
D.C. Hunt ◽  
G. Tuck
Keyword(s):  
Safety Analysis ◽  
Nuclear Safety ◽  
Rocky Flats

Canadian Nuclear Safety Commission: Readiness to Regulate SMRs in Canada

2011 ◽  
Author(s):  
S. Herstead ◽  
M. de Vos ◽  
S. Cook
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Safety Analysis ◽  
Reactor Power ◽  
Nuclear Safety ◽  
Regulatory Framework ◽  
Nuclear Industry ◽  
Plant Design ◽  
Regulatory Documents

The success of any new build project is reliant upon all stakeholders — applicants, vendors, contractors and regulatory agencies — being ready to do their part. Over the past several years, the Canadian Nuclear Safety Commission (CNSC) has been working to ensure that it has the appropriate regulatory framework and internal processes in place for the timely and efficient licensing of all types of reactor, regardless of size. This effort has resulted in several new regulatory documents and internal processes including pre-project vendor design reviews. The CNSC’s general nuclear safety objective requires that nuclear facilities be designed and operated in a manner that will protect the health, safety and security of persons and the environment from unreasonable risk, and to implement Canada’s international commitments on the peaceful use of nuclear energy. To achieve this objective, the regulatory approach strikes a balance between pure performance-based regulation and prescriptive-based regulation. By utilizing this approach, CNSC seeks to ensure a regulatory environment exists that encourages innovation within the nuclear industry without compromising the high standards necessary for safety. The CNSC is applying a technology neutral approach as part of its continuing work to update its regulatory framework and achieve clarity of its requirements. A reactor power threshold of approximately 200 MW(th) has been chosen to distinguish between large and small reactors. It is recognized that some Small Modular Reactors (SMRs) will be larger than 200 MW(th), so a graded approach to achieving safety is still possible even though Nuclear Power Plant design and safety requirements will apply. Design requirements for large reactors are established through two main regulatory documents. These are RD-337 Design for New Nuclear Power Plants, and RD-310 Safety Analysis for Nuclear Power Plants. For reactors below 200 MW(th), the CNSC allows additional flexibility in the use of a graded approach to achieving safety in two new regulatory documents: RD-367 Design of Small Reactors and RD-308 Deterministic Safety Analysis for Small Reactors. The CNSC offers a pre-licensing vendor design review as an optional service for reactor facility designs. This review process is intended to provide early identification and resolution of potential regulatory or technical issues in the design process, particularly those that could result in significant changes to the design or analysis. The process aims to increase regulatory certainty and ultimately contribute to public safety. This paper outlines the CNSC’s expectations for applicant and vendor readiness and discusses the process for pre-licensing reviews which allows vendors and applicants to understand their readiness for licensing.

scholarly journals Study on Typical Design Basis Conditions of HPR1000 With Nuclear Safety Analysis Code ATHLET

2020 ◽  
Vol 8 ◽  
Author(s):  
Xi Huang ◽  
Weixin Zong ◽  
Ting Wang ◽  
Zhikang Lin ◽  
Zhihao Ren ◽  
...  
Keyword(s):  
Safety Analysis ◽  
Nuclear Safety ◽  
Design Basis ◽  
Typical Design

scholarly journals Conditions for the successful integration of Human and Organizational Factors (HOF) in the nuclear safety analysis

Work ◽  
2012 ◽  
Vol 41 ◽  
pp. 2656-2660
Author(s):  
Michèle Tosello ◽  
Françoise Lévêque ◽  
Stéphanie Dutillieu ◽  
Guillaume Hernandez ◽  
Jean-François Vautier
Keyword(s):  
Organizational Factors ◽  
Safety Analysis ◽  
Nuclear Safety ◽  
Human And Organizational Factors ◽  
Successful Integration

scholarly journals Development of Safety Analysis Techniques Applied for Nuclear Safety Examination.

1992 ◽  
Vol 34 (3) ◽  
pp. 227-238
Author(s):  
Masayoshi SHIBA ◽  
Yasukazu ISHIDA ◽  
Tohru HAGA ◽  
Shuji INOUE ◽  
Akito NISHI ◽  
...  
Keyword(s):  
Safety Analysis ◽  
Nuclear Safety ◽  
Analysis Techniques

scholarly journals Status and Assessment Method of Nuclear Safety Analysis Software in China

2021 ◽  
Vol 9 ◽  
Author(s):  
Xinli Gao ◽  
Jianping Jing ◽  
Xiangzhen Han ◽  
Bin Jia ◽  
Xinlu Tian ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Safety Evaluation ◽  
Evaluation Process ◽  
Safety Analysis ◽  
Assessment Method ◽  
Nuclear Safety ◽  
Analysis Software ◽  
Software Safety ◽  
Engineering Software ◽  
Software Applications

In recent years, China’s nuclear power industry has enjoyed a good momentum of development, and related companies have also developed many nuclear analysis software applications. However, as the National Nuclear Safety Administration (NNSA, Chinese nuclear regulatory institution) did not approve any software before 2018, all these software applications were not evaluated formally, so they have not yet been used in reactor safety analysis. In order to solve this problem, in 2018, the National Nuclear Safety Administration started to carry out an engineering applicability evaluation for software developed by Chinese companies. After several years of review, as the first approved Chinese domestic software, core physics analysis software PCM developed by the China General Nuclear Power Group officially passed the software safety evaluation of the China Nuclear Safety Administration. This study will present the basic situation of the development of China’s nuclear power engineering software and introduce the framework, methods, procedures, requirements, and other aspects of China’s software safety evaluation work. The evaluation process and evaluation key issues of PCM software will also be illustrated.

Development of Streamlined Nuclear Safety Analysis Tool for Spent Nuclear Fuel Applications

2017 ◽  
Vol 199 (3) ◽  
pp. 227-244 ◽  
Author(s):  
R. A. Lefebvre ◽  
P. Miller ◽  
J. M. Scaglione ◽  
K. Banerjee ◽  
J. L. Peterson ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Safety Analysis ◽  
Nuclear Safety ◽  
Analysis Tool

Extension of staggered-grid-based AUSM-family schemes for use in nuclear safety analysis codes

2017 ◽  
Vol 93 ◽  
pp. 17-32
Author(s):  
Qiulan Zeng ◽  
Nusret Uğurhan Aydemir ◽  
Fue-Sang Lien ◽  
Tao Xu
Keyword(s):  
Safety Analysis ◽  
Nuclear Safety ◽  
Staggered Grid ◽  
Grid Based

The Analysis of Initiating Events in PSA for TMSR

2016 ◽  
Author(s):  
Jiaxu Zuo ◽  
Jianping Jing ◽  
Wei Song ◽  
Chunming Zhang
Keyword(s):  
Operating Experience ◽  
Safety Analysis ◽  
Nuclear Safety ◽  
Analysis Method ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Analysis And Evaluation ◽  
Key Points ◽  
Analysis Calculation ◽  
High Temperature Reactor

The initiation events analysis and evaluation were the beginning of nuclear safety analysis and probabilistic safety assessment, and it was the key points of the nuclear safety analysis. The main methods of the initiation events analysis are reference to existing lists and reports, operating experience, project evaluation and logic diagrams analysis. Currently, the initiation events analysis method and experiences both focused on pressurized water reactor but there are no general theories for Fluoride Salt-Cooled High Temperature Reactor (FHR). With FHR’s research and development, the initiation events analysis and evaluation was increasingly important. Based on the FHR’s design, the theories and methods of initiation events analysis would be researched and developed. From the FHR’s design, the systems, subsystems and components are divided to identify the safety functions of them. Base on the safety functions, the logical analysis and accident analysis calculation method would be combined to study FHR’s initiation events. The theory of analysis would be developed and the analysis method system would be discussed. Finally, the preliminary initiation events list of FHR will be discussed and researched. The results would help TMSR’s reactor designs and nuclear safety analysis.

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