Nuclear engineering Rethinking nuclear safety management: Injunction as a meta-concept

2014 ◽  
pp. 651-656 ◽  
Keyword(s):  
Safety Management ◽  
Nuclear Safety ◽  
Nuclear Engineering

The Shutdown PSA Model of the TQNPP CANDU Reactor and the Outage Risk Management

2017 ◽  
Author(s):  
Xiaochun Peng ◽  
Qiang Fu ◽  
Yu Han ◽  
Yong Cao
Keyword(s):  
Risk Assessment ◽  
Risk Management ◽  
Low Power ◽  
Safety Management ◽  
Nuclear Safety ◽  
Management Guideline ◽  
Working Plan ◽  
Assessment Result

This paper presents the characteristic of Outage Nuclear Safety Management Guideline (ONSMG) for Qinshan CANDU plant and the introduction of shutdown and low-power PSA (SPSA) of TQNPP. The SPSA model is used to assess the outage configuration risk of OT109. The result and its risk insight are discussed about the two different outage working plan. In conclusion, the risk of nuclear safety and the economic are discussed based on the risk assessment result.

scholarly journals CANDU Safety R&D Status, Challenges, and Prospects in Canada

2015 ◽  
Vol 2015 ◽  
pp. 1-9
Author(s):  
W. Shen ◽  
F. Doyle
Keyword(s):  
Nuclear Safety ◽  
Atomic Energy ◽  
Light Water Reactor ◽  
Current Status ◽  
Nuclear Engineering ◽  
Safe Operation ◽  
Future Directions ◽  
Light Water ◽  
Safety Research ◽  
Canada Limited

In Canada, safe operation of CANDU (CANada Deuterium Uranium; it is a registered trademark of Atomic Energy of Canada Limited) reactors is supported by a full-scope program of nuclear safety research and development (R&D) in key technical areas. Key nuclear R&D programs, facilities, and expertise are maintained in order to address the unique features of the CANDU as well as generic technology areas common to CANDU and LWR (light water reactor). This paper presents an overview of the CANDU safety R&D which includes background, drivers, current status, challenges, and future directions. This overview of the Canadian nuclear safety R&D programs includes those currently conducted by the COG (CANDU Owners Group), AECL (Atomic Energy of Canada Limited), Candu Energy Inc., and the CNSC (Canadian Nuclear Safety Commission) and by universities via UNENE (University Network of Excellence in Nuclear Engineering) sponsorship. In particular, the nuclear safety R&D program related to the emerging CANDU ageing issues is discussed. The paper concludes by identifying directions for the future nuclear safety R&D.

Reform of Nuclear Safety Education for Non-Nuclear Engineering Students

2010 ◽  
Author(s):  
Qinghai Luo ◽  
Zhuying Zou
Keyword(s):  
Safety Culture ◽  
Education System ◽  
Engineering Students ◽  
Radioactive Source ◽  
Nuclear Safety ◽  
Nuclear Industry ◽  
Nuclear Engineering ◽  
Nuclear Accidents ◽  
Safety Education ◽  
Nuclear Development

The new situations were analyzed for nuclear development and security. Besides nuclear wars and terrorism, reactor runaway and un-ruled radioactive source are the main nuclear accidents in peacetime. With the active development of the nuclear cause in China, the nuclear education system is becoming deficient or defective. In order to ensure the sustainable and efficient accord development of nuclear industry, general nuclear education is necessary for correlative non-nuclear professionals, such as technologies, management, safety, culture and ethic.

Safety Basis Design Development Challenges

2007 ◽  
Author(s):  
Jonathan Young ◽  
Pete Lowry ◽  
Bruce Schmitt ◽  
Robin Sullivan ◽  
Lenna Mahoney ◽  
...  
Keyword(s):  
Spent Nuclear Fuel ◽  
Safety Management ◽  
Safety Analysis ◽  
Nuclear Safety ◽  
Department Of Energy ◽  
Design Activity ◽  
Design Development ◽  
Design Basis ◽  
Safety Features ◽  
System 1

“Designing in Safety” is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.1B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation 10CFR830, Nuclear Safety Management. 10CFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE’s Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, 1) flashing spray leaks and 2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

scholarly journals Forecast of China’s Future Nuclear Energy Development and Nuclear Safety Management Talents Development

2021 ◽  
Vol 691 (1) ◽  
pp. 012022
Author(s):  
LI Xiao-ding ◽  
QU Yun-huan ◽  
ZHANG Li-hui ◽  
GONG Yu ◽  
DONG Yi-man ◽  
...  
Keyword(s):  
Nuclear Energy ◽  
Safety Management ◽  
Energy Development ◽  
Nuclear Safety

Safety Management And Safety Culture In The U.S. Construction Industry

2017 ◽  
Author(s):  
Xiuwen Sue Dong ◽  
Xuanwen Wang ◽  
Rebecca Katz
Keyword(s):  
Construction Industry ◽  
Safety Culture ◽  
Safety Management ◽  
The U.S
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