Development and usage of the digital SAMG system

Kerntechnik ◽  
2021 ◽  
Vol 86 (3) ◽  
pp. 224-228
Author(s):  
Y. Chen ◽  
M. Wang ◽  
C. He ◽  
L. Li ◽  
W. Yang
Keyword(s):  
Information Technology ◽  
Severe Accident ◽  
Mitigation Measures ◽  
Management Guidelines ◽  
Accident Management ◽  
Software And Hardware ◽  
Digital Processes ◽  
Work Burden

Abstract In order to reduce the work burden during the training and drilling of the severe accident and severe accident management guidelines, and improve the implementation efficiency of the guidelines, a method of digitizing the SAMG program files is proposed. A set of digital SAMG system supported by information technology and combined with software and hardware is developed to transform the manual processes of paper file browsing, data searching, logical judgment and auxiliary calculation into automatic and digital processes, which can be used for SAMG training and drilling, and also for verifying the SAMG execution process and the effectiveness of mitigation measures.

scholarly journals ELIMINASI RISIKO OPERASIONAL BMT SRI SEJAHTERA SURABAYA

2020 ◽  
Vol 6 (7) ◽  
pp. 1317
Author(s):  
Yanuar Dharma Putra ◽  
Imron Mawardi
Keyword(s):  
Information Technology ◽  
Human Resources ◽  
Risk Mitigation ◽  
Computer Software ◽  
Mitigation Measures ◽  
Job Description ◽  
Information Risk ◽  
Software And Hardware ◽  
Moral Guidance

The results of this research are risk mitigation measures in the continuity of internal processes, human resources, technology and information. Risk mitigation on the internal processes is done by performing supervision based on employees job description, and implementation of sharia financing agreements with customers. Risk mitigation on human resources is done by providing moral guidance to employees. Risk mitigation in information technology is carried out by performing regular maintenance of computer software and hardware, as well as other devices that support Baitul Maal wa tamwil Sri Sejahtera business activities.

Issues Associated With the Development of Severe Accident Management Guidelines for NPPs in China

2013 ◽  
Author(s):  
Zhiyi Yang ◽  
Yimin Chong ◽  
Chun Li ◽  
Jian Deng ◽  
Xianhong Xu ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Severe Accident ◽  
Regulatory Body ◽  
Control Room ◽  
Technical Approach ◽  
Management Guidelines ◽  
Accident Management ◽  
Term Monitoring

After Fukushima nuclear accident, the Severe Accident Management Guidelines (SAMGs) are required according to the policy of the regulatory body in China. Most nuclear power plants (NPPs) in China adopt the technical approach of generic-SAMG of the Westinghouse Owner Group, consisting of severe accident control room guideline (SACRG), diagnostic flow chart (DFC), severe accident guideline (SAG), severe challenge status tree (SCST), severe challenge guideline (SCG), technical support center (TSC) long term monitoring guideline, and SAMG termination guideline (SAEG). A number of issues have been identified during the development of the SAMGs for M310+ NPPs, which is a dominant reactor type in China. The paper discussed these issues and identified some considerations for their resolution.

Study on the Accidental Rupture of Hot Leg or Surge Line in SBO Accident

2006 ◽  
Author(s):  
Kun Zhang ◽  
Xuewu Cao
Keyword(s):  
Pressure Vessel ◽  
Severe Accident ◽  
Base Case ◽  
Management Guidelines ◽  
Accident Management ◽  
Lower Head ◽  
Station Blackout ◽  
Surge Line ◽  
Reactor Pressure ◽  
Relap5 Code

The postulated total station blackout accident (SBO) of PWR NPP with 600 MWe in China is analyzed as the base case using SCDAP/RELAP5 code. Then the hot leg or surge line are assumed to rupture before the lower head of Reactor Pressure Vessel (RPV) ruptures, and the progressions are analyzed in detail comparing with the base case. The results show that the accidental rupture of hot leg or surge line will greatly influence the progression of accident. The probability of hot leg or surge line rupture in intentional depressurization is also studied in this paper, which provides a suggestion to the development of Severe Accident Management Guidelines (SAMG).

Problems With Cooling of Overheated Fuel Channels in RBMK-Type Reactors

2008 ◽  
Author(s):  
Eugenijus Uspuras ◽  
Algirdas Kaliatka
Keyword(s):  
Heat Removal ◽  
Water Source ◽  
Severe Accident ◽  
Management Guidelines ◽  
Management Measures ◽  
Accident Management ◽  
Feed Strategy ◽  
Significant Probability ◽  
Reactor Types

One of the most dangerous beyond design basis accidents for all types of nuclear reactors is the loss of long-term heat removal from the core. In RBMK-type reactors, this initiating event, which can lead to the worst consequences, has significant probability to occur in comparison to other type of BDBA. The most effective accident mitigation measure in this case is “bleed and feed” strategy — similar as is recommended for other light water reactor types. In this paper the challenges, which are meet in case of cooling of overheated fuel channels in RBMK-type reactors, are discussed. The simulation results of BDBA using RELAP5/MOD3.3 code are presented. Accident management measures (de-pressurization of reactor cooling circuit and injection of water from non-regular water source) are evaluated in respect of dangerous pressure increase and thermal shock in fuel channels. These results were used during development of severe accident management guidelines for RBMK-1500 at Ignalina NPP.

Innovative Practice of Severe Accidents Measures in CAP1400

2017 ◽  
Author(s):  
Likai Fang ◽  
Xin Liu ◽  
Guobao Shi
Keyword(s):  
Nuclear Power ◽  
Heat Removal ◽  
Severe Accident ◽  
Mitigation Measures ◽  
Spent Fuel ◽  
Fukushima Accident ◽  
Power Sources ◽  
Severe Accidents ◽  
Accident Management ◽  
Accident Conditions

CAP1400 is GenIII passive PWR, which was developed based on Chinese 40 years of experience in nuclear power R&D, construction&operation, as well as introduction and assimilation of AP1000. Severe accidents prevention and mitigation measures were systematically considered during the design and analysis. In order to accommodate high power and further improve the safety of the plant, also considering feedback from Fukushima accident, some innovative measures and design requirements were also applied. Based on the probabilistic&deterministic analysis and engineering judgment, considerable severe accidents scenarios were considered. Both severe accidents initiated at power and shutdown condition were analyzed. Insights were also obtained to decide the challenge to the plant. All known severe accidents phenomena and their treatment were considered in the design. In vessel retention (IVR) was applied as one of the severe accident mitigation measures. To improve the margin of IVR success and verify the heat removal capability through reactor pressure vessel, both design innovative measures and experiments were used. The melt pool behavior and corium pool configuration were also studied by using CFD code and thermodynamic code. Hydrogen risk was mitigated by installation of hydrogen igniters, which were comprised of two serials, and were powered by multiple power sources. To further improve the safety, six extra hydrogen passive recombiners were also added in the containment. Hydrogen risk was analyzed both inside containment and outside containment considering leakage effect. Other severe accident phenomena were also considered by designed or analyzed to show the containment robustness to accommodate it. As one of the Fukushima accident feedback, full scope severe accident management guideline were developed by considering both power condition and shutdown condition, accident management for spent fuel pool was also considered. As the basis of accident management during severe accidents, survivability of equipments and instruments that are necessary in severe accident were assessed and will be further tested and/or analyzed. Such tests will consider severe accident conditions arised from hydrogen combustion.

scholarly journals Analysis of Fuel Criticality during Severe Accidents

2015 ◽  
pp. 3-8
Author(s):  
I. Bilodid ◽  
J. Duspiva
Keyword(s):  
Severe Accident ◽  
Stress Tests ◽  
Fukushima Accident ◽  
Management Guidelines ◽  
Severe Accidents ◽  
Design Basis ◽  
Accident Management ◽  
The World ◽  
Criticality Safety

Interest in the analysis of beyond design basis accidents, involving a combination of several failures with fuel damage, has increased throughout the world after the Fukushima accident. Stress tests were performed at NPPs, and development of severe accident management guidelines was started. These activities necessitated calculations to analyze the probability of beyond design basis accidents and assess their initiating events and consequences. One of the aspects in analysis of beyond design basis accidents is to determine the potential for re-criticality during such accidents. The paper provides results of some criticality safety calculations for VVER reactors performed, in particular, by ÚJV Řež and SSTC NRS experts. It is shown how criticality can occur in different severe accident phases.

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