Abstract
The optimization measures in the physical protection system monitoring center of a nuclear power plant include the prioritization of alarm signals, optimization of sound and light alarm form, improvement of the layout of video monitor screen, security training, and strengthening of organizational management. Based on the fuzzy analytic hierarchy process, the influence of these factors on the probability of alert assessment and guard’s respond time in the EASI method are quantitatively analyzed. Making full use of the measures for prioritization of alarm signals can effectively promote the improvement of human-computer interaction efficiency. The degree of influence of the four factors (guarder’s status, decision strategy, guarder’s training and organization management) on guard’s decision-making is roughly the same.
Kurzfassung
Zu den Optimierungsmaßnahmen in der Überwachungszentrale des Sicherungssystems eines Kernkraftwerks gehören die Priorisierung von Alarmsignalen, die Optimierung der Ton- und Lichtalarmformen, die Verbesserung des Layouts des Videomonitorbildschirms, Sicherheitstraining und die Stärkung des Organisationsmanagements. Basierend auf dem Verfahren der unscharfen analytischen Hierarchie wird der Einfluss dieser Faktoren auf die Wahrscheinlichkeit der Alarmbewertung und die Reaktionszeit des Wachpersonals in der EASI-Methode quantitativ analysiert. Die volle Ausschöpfung der Maßnahmen zur Priorisierung von Alarmsignalen kann die Verbesserung der Effizienz der Mensch-Computer-Interaktion wirksam fördern. Der Grad des Einflusses der vier Faktoren (Status des Wächters, Entscheidungsstrategie, Ausbildung des Wächters und Organisationsmanagement) auf die Entscheidungsfindung des Wächters ist ungefähr gleich.
References
1 International Atomic Energy Agency: Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities. Nuclear security series no. 13. Vienna, Austria: International Atomic Energy Agency; 2015Search in Google Scholar
2 Liu, Y.; Cheng, X.: Characteristics Analysis of Physical Protection System in Nuclear Power Plant. Electrical applications 12 (2011) 62 –65Search in Google Scholar
3 Garcia, M. L.: Design and evaluation of physical protection systems. Butterworth-Heinemann, Burlington (2007) 89Search in Google Scholar
4 O’Connor, S. L.; Whitehead, D. W.; Potter III, C. S.: Nuclear power plant security assessment technical manual. Sandia National Laboratories (2007) 26, DOI:10.2172/92172210.2172/921722Search in Google Scholar
5 Garcia, M. L.: Vulnerability assessment of physical protection systems. Butterworth-Heinemann, Burlington (2005) 151–152Search in Google Scholar
6 Wadoud, A. A.; Adail, A. S.; Saleh, A. A.: Physical protection evaluation process for nuclear facility via sabotage scenarios. Alexandria Engineering Journal 57 (2018) 831–839, DOI:10.1016/j.aej.2017.01.04510.1016/j.aej.2017.01.045Search in Google Scholar
7 Bennett, H. A.: EASI approach to physical security evaluation. SAND-76–0500, Sandia National Laboratory, Albuquerque (1977)Search in Google Scholar
8 Sandia National Laboratory: SAVI: Systematic Analysis of Vulnerability to Intrusion, SAND89–0926, Sandia National Laboratory, Albuquerque (1989)Search in Google Scholar
9 Vintr, Z.; Vintr, M.; Malach, J.: Evaluation of physical protection system effectiveness, 2012 IEEE International Carnahan Conference on Security Technology (ICCST), IEEE (2012) 15–21, DOI:10.1109/CCST.2012.639353210.1109/CCST.2012.6393532Search in Google Scholar
10 Liu, Y.: Analysis and improvement of physical protection system operation of nuclear power station. Progress Report on China Nuclear Science & Technology, Vol. 4. Volume 10 of the 2015 Annual Conference of the Chinese Nuclear Society (Nuclear Safety Volume) (2015) 140–150Search in Google Scholar
11 Vaidya, O. S.; Kumar, S.: Analytic hierarchy process: An overview of applications. European Journal of operational research 169 (2006) 1–29, DOI:10.1016/j.ejor.2004.04.02810.1016/j.ejor.2004.04.028Search in Google Scholar
12 Junior, F. R. L.; Osiro, L.; Carpinetti, L. C. R.: A comparison between Fuzzy AHP and Fuzzy TOPSIS methods to supplier selection. Applied Soft Computing 21 (2014) 194–209, DOI:10.1016/j.asoc.2014.03.01410.1016/j.asoc.2014.03.014Search in Google Scholar
13 Pengcheng, L. I.; Guohua, C.; Li, Z.; et al.: Analysis of influencing factors triggering operator’s error in nuclear power plants. China Safety Science Journal (2017) 42–47Search in Google Scholar
14 Liu, P.; Zheng, M.: Analysis of human error and dynamic progressing model of human error in NPP. Nuclear Safety (Beijing) (2010) 51–58Search in Google Scholar
15 Shu-Dong, H, et al.: Quantified Decision-making for Prevention of Accident Caused by Human Factor in Nuclear Power Plant. China Safety Science Journal (2006)Search in Google Scholar
© 2021 Walter de Gruyter GmbH, Berlin/Boston, Germany
Articles in the same Issue
- Frontmatter
- The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition
- Establishment of analysis methodology of RADTRAD for Maanshan PWR ATWS
- Calendar of Events
- CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle
- Effectiveness assessment of improvement measures in physical protection system monitoring center
- A study on accumulator analysis for the valve performance evaluation system of nuclear power plants
- Calculation studies of coated particles performance in sodium-cooled fast reactor
- Effect of using graphene/water based nanofluid on heat transfer in heat exchangers with rotating straight inner tube
- Radiation shielding properties of mortars containing heavyweight particles
- Improvement of the passive efficiency calibration of the segmented gamma scanner
- Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Establishment of analysis methodology for ionizing mattresses using RESRAD-BUILD code
- Editorial
Articles in the same Issue
- Frontmatter
- The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition
- Establishment of analysis methodology of RADTRAD for Maanshan PWR ATWS
- Calendar of Events
- CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle
- Effectiveness assessment of improvement measures in physical protection system monitoring center
- A study on accumulator analysis for the valve performance evaluation system of nuclear power plants
- Calculation studies of coated particles performance in sodium-cooled fast reactor
- Effect of using graphene/water based nanofluid on heat transfer in heat exchangers with rotating straight inner tube
- Radiation shielding properties of mortars containing heavyweight particles
- Improvement of the passive efficiency calibration of the segmented gamma scanner
- Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Establishment of analysis methodology for ionizing mattresses using RESRAD-BUILD code
- Editorial