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Seminar on The Reactor Safety Analysis: Deterministic versus Probabilistic
 


Date, time & venue

2018-04-10;6:30pm;Room 1511, 1/F, Li Dak Sum Yip Yio Chin Academic Building, City University of Hong Kong, Kowloon Tong, Hong Kong


Seminar on The Reactor Safety Analysis: Deterministic versus Probabilistic


Organizer: HKIE-Nuclear Division

Supporting Organizer: City University of Hong Kong, Department of Mechanical and Biomedical Engineering, & Hong Kong Nuclear Society


Date, Time and Venue

10 April 2018 (Tuesday); 6:30 p.m.; Room 1511, 1/F, Li Dak Sum Yip Yio Chin Academic Building, City University of Hong Kong, Kowloon Tong, Hong Kong


Programme Highlights

In the reactor safety analysis, both deterministic and probabilistic methods are used. In this seminar, both methods currently used in the nuclear industry will be introduced and discussed. Firstly, the deterministic method with the nine categories of design basis nuclear accidents analyzed in the Final Safety Analysis Report (FSAR) will be introduced. After that, the probabilistic risk assessment (PRA) will be addressed together with the introduction on WASH-1400, the pioneering safety analysis report using PRA. Finally, some CityU researches on severe accidents will be presented.

 

Speaker

Dr. Zhao JiYun is currently an associate professor in Nuclear and Risk Engineering Program at City University of Hong Kong and a member of American Nuclear Society.


Registration and Enquiries

The seminar is free of charge and prior registration is required. The number of participants will be limited to 80 and applicants will be accepted on a first-come-first-served basis. Priority will be given to the members of Nuclear Division. For registration, please complete and return the Standard Reply Form to Ms Annie KOU via Email: nuclear@ne.hkie.org.hk by 6 April 2018 Successful applicants will be notified by emails. For enquiries, please contact Ms Annie KOU at nuclear@ne.hkie.org.hk.


Disclaimer

All information and views expressed by speakers and in their conference materials do not reflect the official opinion and position of HKIE. No responsibility is accepted by the HKIE or their publisher for such information and views including their accuracy, correctness and veracity.






Report

Seminar on "Reactor Safety Analysis: Deterministic versus Probabilistic”

Prepared by Mr Paul Y H Wang

A technical seminar was organized by the Nuclear Division on “Reactor Safety Analysis: Deterministic versus Probabilistic” on 10 April 2018 at the City University of Hong Kong. The seminar was presented to around 30 participants by Dr. Zhao JiYun, Associate Professor in Nuclear and Risk Engineering program at the university.

While reactors may differ greatly in design and detailed engineering characteristics, they share certain basic design safety principles, including the multiple-barrier concept for fission-product containment and its related defense-in-depth. The defense-in-depth philosophy mandates safety systems that are independent, diverse, and redundant. However, this philosophy does not identify the level of redundancy needed. To make these decisions, both deterministic and probabilistic methods are used in the reactor safety analysis. The Deterministic Risk Assessment (DRA) uses postulated accidents and the single failure criterion. In contrast, the Probabilistic Risk Assessment (PRA) take a holistic approach which evaluates risks associated with every life-cycle aspect of a engineering entity from concept definition, through design, construction and operation, and up to decommissioning.

As a probabilistic safety goal, the US Nuclear Regulatory Commission (NRC) issued the Quantitative Health Objectives (QHO) specifying the risk from a nuclear power plant to be less than 1/1000th of the total risk for those living near the plant. The pioneering report WASH-1400 in 1975 that assessed accident risk of US commercial nuclear power plants was the first attempt to provide a realistic and systematic assessment of their risks. Despite subsequent refinements, the basic probabilistic risk assessment (PRA) approach promulgated in WASH-1400 is still relevant today. Dr. Zhao JiYun also went to some lengths to illustrate current nuclear research at the university.

In conclusion, the seminar was very fruitful and of special interest to the members for an insight into the Reactor Safety Analysis. On behalf of the Nuclear Division, we wish to express our sincere gratitude to Dr. Zhao JiYun for providing this informative seminar to our members.


Photo caption: Dr. Zhao JiYun (right) receiving a souvenir from Ir Ryan Lam, Deputy Chairman of the Nuclear Division

 

 
 

 

 
 
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