Design and Development of the Platform for Significance Determination Process System for Nuclear Power Plant

2018 ◽  
Author(s):  
Qinfang Zhang ◽  
Guoxu Zhang ◽  
Zilong Wang ◽  
Qi Dong ◽  
Guofeng Tang
Keyword(s):  
Power Plant ◽  
Risk Evaluation ◽  
Nuclear Power ◽  
Important Application ◽  
Design And Development ◽  
Whole Process ◽  
Event Risk ◽  
Determination Process ◽  
Process System ◽  
And Performance

Significance determination process (SDP) is one of important application tools in the scheme of risk-informed and performance based regulation. It is used to help the analyst evaluate the risk significance of a particular safety concerned event. By referring to the design and development of SDP system, this paper gives a brief introduction on the design and development of the system. An autonomously developed PSA quantification engine is incorporated into the SDP system, and it helps to resolve quantification issue for event risk evaluation. From qualified screening to risk significance quantification, SDP system is designed to realize the whole process for event risk analysis. SDP system could potentially help analysts from both regulatory agency and NPP licensees to quickly evaluate the risk significance of a particular event.

Implications of Nuclear Power Plant Regulation for Future Nuclear Plants Based on Risk and Performance Information

2009 ◽  
Author(s):  
Mohammad Modarres
Keyword(s):  
Power Plant ◽  
Nuclear Power ◽  
Probabilistic Assessment ◽  
Performance Information ◽  
Confidence Levels ◽  
Probability Bounds ◽  
Nuclear Plants ◽  
Plant Operations ◽  
And Performance ◽  
Regulatory Acceptance

A largely probabilistic regulatory framework using best estimate, goal-driven, risk-informed, and performance-based methods is proposed. This framework relies on continuous probabilistic assessment of performance of plant systems, structures, components and operators that assure attainment of a broad set of overarching technology-neutral protective, mitigative, and preventive goals in all phases of plant operations. Required levels of performance are set through formal apportionment such that they are consistent with the overarching goals. Regulatory acceptance would be based on the probability bounds or confidence levels with which the required levels of performance have been attained.

The Application of Risk-Informed-Inservice Inspection to Recirculation Piping Welds of a Nuclear Power Plant

2007 ◽  
Vol 120 ◽  
pp. 213-222
Author(s):  
K.C. Hsieh ◽  
Kung Ting ◽  
Kuen Tsan Chen ◽  
W.F. Wu ◽  
Y.L. Lu
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Dose Reduction ◽  
Risk Evaluation ◽  
Nuclear Power ◽  
Safety Concern ◽  
Substantial Cost ◽  
Plant Maintenance ◽  
Cost Reductions

The implementations of RI-ISI can improve the substantial cost reductions as well as dose reduction. From the points of the safety concern, the achievements of these procedures can identify the inspection rank to promote the integrity of the present inspection program. Thus, this paper presents the applications of RI-ISI to recirculation piping welds sensitized to IGSCC of Taiwan BWR-4 nuclear power plant. The establishment of the risk evaluation can be referenced for the regulatory and plant maintenance.

Research on Adsorption Performance of Type III Adsorber Used in Nuclear Power Plant

2013 ◽  
Author(s):  
Xin Xu ◽  
Lian-tao Yu
Keyword(s):  
Power Plant ◽  
Performance Analysis ◽  
Nuclear Power Plant ◽  
Test Data ◽  
Nuclear Power ◽  
Performance Test ◽  
Type Iii ◽  
Adsorption Performance ◽  
Test Platform ◽  
And Performance

Based on operational principle and performance analysis of type III adsorber, a set of test platform for type III adsorber adsorption performance test is designed. After testing of the prototype and analyzing the test data, it is concluded that the prototype is qualified to be used in nuclear power plant and it fills the gap in China.

Maximizing Value of Existing Nuclear Power Plant Generating Assets: A Case Study

2007 ◽  
Author(s):  
Komandur S. Sunder Raj
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Fossil Fuels ◽  
Nuclear Facilities ◽  
Operation Performance ◽  
Generating Capacity ◽  
Greenhouse Effects ◽  
And Performance

The nuclear power industry is presently witnessing a renaissance. Global warming, greenhouse effects, concerns with use of as well as rising costs of fossil fuels, the desire to be weaned from foreign oil are all factors driving the need for increased reliance on nuclear power. Consequently, nuclear power plant owners are seeking to maximize the value of their generating assets through various means: improved operation, performance, capacity, availability, reliability and efficiency; license renewals, and; power uprates. Capacity factors are currently averaging well over 90% and, forced outage rates have decreased significantly, reflecting the maturation of operating and maintenance practices. In recognition of low fuel and relatively stable operating costs of their nuclear facilities, nuclear power plant owners have not only applied for license renewals, but have also upgraded the operation and, added electrical generating capacity to the operating units. Using a case study, this paper describes current efforts in maximizing the value of existing nuclear power plant generating assets. The focus of the paper is on maximizing benefits through improved operations and performance.

scholarly journals Design and Development Framework of Safety-Critical Software in HTR-PM

2017 ◽  
Vol 2017 ◽  
pp. 1-9 ◽  
Author(s):  
Chao Guo ◽  
Huasheng Xiong ◽  
Xiaojin Huang ◽  
Duo Li
Keyword(s):  
Power Plant ◽  
Software Design ◽  
Nuclear Power ◽  
Software Verification ◽  
Software Test ◽  
Release Time ◽  
Design And Development ◽  
Efficient Operation ◽  
Development Framework ◽  
Software Release

With the development of information technology, the instrumentation and control system of nuclear power plant nowadays rely heavily on the massive and complex software to ensure the safe and efficient operation of the power plant. The improvement of the software design and development for the safety systems has been a research focus for its decisive impact on the nuclear safety. The framework of the software design and development for reactor protection system in High Temperature Gas-Cooled Reactor-Pebble bed Module was introduced in this paper. Firstly, during the design period, in addition to multichannel redundancy, grouping of protection variables and diverse 2-out-of-4 logics were adopted by different subsystems of each channel in case of common cause failure. Then a series of development characteristics together with strict software verification and validation were performed. Thirdly, during the software test period, an improved software reliability growth model based on the Goel-Okumoto model according to the analysis of fault severity was proposed to help in estimating the reliability of the software product and identifying the software release time.

Very High Efficiency Small Nuclear Gas Turbine Power Plant Concept (HTGR-GT/BC) for Special Applications

1984 ◽  
Author(s):  
C. F. McDonald ◽  
L. Cavallaro ◽  
D. Kapich ◽  
W. A. Medwid
Keyword(s):  
Power Plant ◽  
Gas Turbine ◽  
Nuclear Power ◽  
High Efficiency ◽  
Early Stage ◽  
Power Conversion ◽  
Combined Cycle ◽  
Conversion System ◽  
And Performance ◽  
Plant Efficiency

To meet the energy needs of special terrestrial defense installations, where a premium is placed on high plant efficiency, conceptual studies have been performed on an advanced closed-cycle gas turbine system with a high-temperature gas-cooled reactor (HTGR) as the heat source. Emphasis has been placed on system compactness and plant simplicity. A goal of plant operation for extended periods with no environmental contact had a strong influence on the design features. To realize a high plant efficiency (over 50%) for this mode of operation, a combined cycle was investigated. A primary helium Brayton power conversion system coupled with a Freon bottoming cycle was selected. The selection of a gas turbine power conversion system is very much related to applications where high efficiency is paramount and this can be realized with the utilization of a cold heat sink. Details are presented of the reactor arrangement, power conversion system, major components, installation, and performance for a compact nuclear power plant currently in a very early stage of concept definition.

Improving the reliability and performance of a nuclear power plant by using computers in control systems

1989 ◽  
Vol 66 (6) ◽  
pp. 479-483
Author(s):  
F. M. Mitenkov ◽  
V. V. Vasil'eva ◽  
V. S. Vostokov ◽  
V. S. Gorbunov ◽  
N. P. Zaets ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Control Systems ◽  
Nuclear Power ◽  
And Performance
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