Platform Development and Application of Revision and Review Support System for Safety Important Items in Nuclear Power Plant

Seismic safety is one of the major key issues of nuclear power plant safety in Japan. It is demonstrated that nuclear piping possesses large safety margins through the piping and support system test, which consisted of three dimensional piping, supports, U-bolts, and concrete anchorages, using the E-defense vibration table of National Research Institute for Earth Science and Disaster Prevention, Hyogo Earthquake Engineering Research Center, on extremely high seismic excitation level [1,2,3]. In the above test, the non-linear hysteretic behaviors of the support are quite complicated, but the dissipated energies introduce large damping effects on the piping system response. In order to evaluate the inelastic behavior of the support with respect to the whole piping system response, the following simulation methodology for the support re-evaluation is proposed. 1) Non-linear modeling of the support: • Failure mode and failure capacity of each support. • Simplified non-linear modeling of each support. 2) Simulation Analysis of the piping and support system: • Considering the non-linearity both of the supports and elbows in the piping system. 3) Evaluation of seismic margin: • Focused on the failure level for the support system, and the fatigue damage for the strain range of the piping. The limit state analysis of the typical piping system of a nuclear power plant is presented in this paper, and it is demonstrated that these evaluations of the seismic margins would give important insight into the support reinforcement program on the seismic re-evaluation work.

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Research and Improvement on Characteristics of Emergency Diesel Generating Set Mechanical Support System in Nuclear Power Plant

IOP Conference Series Materials Science and Engineering ◽

10.1088/1757-899x/207/1/012074 ◽

2017 ◽

Vol 207 ◽

pp. 012074

Author(s):

Yang Zhe

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Support System ◽

Nuclear Power ◽

Mechanical Support ◽

Generating Set

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APPLICATION OF DECISION SUPPORT SYSTEM JRODOS FOR ASSESSMENTS OF ATMOSPHERIC DISPERSION AND DEPOSITION FROM FUKUSHIMA DAIICHI NUCLEAR POWER PLANT ACCIDENT

International Journal of Energy for a Clean Environment ◽

10.1615/interjenercleanenv.2013006151 ◽

2012 ◽

Vol 13 (1-4) ◽

pp. 179-190 ◽

Cited By ~ 2

Author(s):

Ievgen O. Ievdin ◽

Oleksandr V. Khalchenkov ◽

Ivan V. Kovalets ◽

Wolfgang Raskob ◽

Dmytro Trybushnyi ◽

...

Keyword(s):

Decision Support ◽

Power Plant ◽

Nuclear Power Plant ◽

Decision Support System ◽

Support System ◽

Nuclear Power ◽

Atmospheric Dispersion ◽

Nuclear Power Plant Accident ◽

Fukushima Daiichi

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Computerized Operator Support System for Nuclear Power Plant Hybrid Main Control Room

Proceedings of the Human Factors and Ergonomics Society Annual Meeting ◽

10.1177/1071181319631532 ◽

2019 ◽

Vol 63 (1) ◽

pp. 1814-1818

Author(s):

Roger Lew ◽

Ronald L. Boring ◽

Thomas A. Ulrich

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Support System ◽

Situation Awareness ◽

Nuclear Power ◽

Power Plants ◽

Prototype System ◽

Control Room ◽

Machine Interface ◽

Plant Hybrid

A Computerized Operator Support System (COSS) is an operator assistive technology that aids operators in monitoring processes to detect off-normal conditions, diagnose plant faults, predict future plant states, recommend mitigation alternatives, and select appropriate mitigation actions. The COSS works in collaboration with an advanced prognostics system called PROAID. The COSS provides a human-machine interface to help operators maintain situation awareness and detect faults earlier than would be possible using conventional control room technologies at nuclear power plants. Here we describe a third-iteration of efforts to develop and validate the COSS. The COSS has now been implemented as a prototype system for a full-scope nuclear power plant simulator. To date, two studies involving three licensed reactor crews were conducted to evaluate the COSS. Here we capture insights into the development of COSS as well as operator feedback and future development guidance derived from the operator-in-the-loop simulator studies.

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