scholarly journals Technical evaluation of the proposed design modifications and technical specification changes for the R. E. Ginna Nuclear Power Plant, Unit 1

1980 ◽  
Author(s):  
J.C. Selan
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technical Specification ◽  
Technical Evaluation ◽  
Nuclear Power Plant Unit

RELIABILITY BASED OPTIMIZATION OF TECHNICAL SPECIFICATION OF FRONTLINE SYSTEMS OF NUCLEAR POWER PLANTS USING MULTI-OBJECTIVE APPROACH

2012 ◽  
Vol 19 (01) ◽  
pp. 1250002
Author(s):  
G. SRINIVAS ◽  
A. K. VERMA ◽  
A. SRIVIDYA ◽  
SANJAY KUMAR KHATTRI
Keyword(s):  
Genetic Algorithm ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technical Specification ◽  
Multi Objective Optimization ◽  
Potential Core ◽  
Multi Objective ◽  
Genetic Algorithm Approach ◽  
Technical Specifications

Technical Specifications define the limiting conditions of operation, maintenance and surveillance test requirements for the various Nuclear Power plant systems in order to meet the safety requirements to fulfill regulatory criteria. These specifications impact even the economics of the plant. The regulatory approach addresses only the safety criteria, while the plant operators would like to balance the cost criteria too. The attempt to optimize both the conflicting requirements presents a case to use Multi-objective optimization. Evolutionary algorithms (EAs) mimic natural evolutionary principles to constitute search and optimization procedures. Genetic algorithms are a particular class of EA's that use techniques inspired by evolutionary biology such as inheritance, mutation, natural selection and recombination (or cross-over). In this paper we have used the plant insights obtained through a detailed Probabilistic Safety Assessment with the Genetic Algorithm approach for Multi-objective optimization of Surveillance test intervals. The optimization of Technical Specifications of three front line systems is performed using the Genetic Algorithm Approach. The selection of these systems is based on their importance to the mitigation of possible accident sequences which are significant to potential core damage of the nuclear power plant.

Study of the Characteristic Response of Pressure Control System in Order to Obtain the Design Parameters of the New Control System MARK VI Turbine in Cofrentes Nuclear Power Plant

2010 ◽  
Author(s):  
Laura Bucho´ ◽  
Mari´a Jose´ Palomo ◽  
Juan Ignacio Vaquer ◽  
Bele´n Lo´pez ◽  
Gregorio Rui´z ◽  
...  
Keyword(s):  
Control System ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Technical Specification ◽  
Pressure Control ◽  
Design Parameters ◽  
Sensor Signal ◽  
Bode Plot ◽  
Pressure Control System

This paper presents the results obtained from the IBE-CNC/DAQ-090827 project, conducted by the company “Titania Servicios Tecnolo´gicos, S.L.” in collaboration with the “Instituto de Seguridad Industrial, Radiofi´sica y Medioambiental” (ISIRYM), in the “Universidad Polite´cnica de Valencia”, for the company “Iberdrola Generacio´n S.A”. The objective is the acquisition of the pressure sensor signal and the measurement at points C85 and N32 from the cabin of the Turbine Control System in Cofrentes Nuclear Power Plant. With the study of previous data, one can obtain the Bode plot of the crossed signals as requested in the technical specification IM 0191 I. Frequency response (i.e. how the system varies its gain and offset depending on the frequency) defines the dynamics.

Risk Based Inspection Pilot Study of Ignalina Nuclear Power Plant, Unit 2

2002 ◽  
Author(s):  
Bjorn Brickstad ◽  
Adam Letzter ◽  
Arturas Klimasauskas ◽  
Robertas Alzbutas ◽  
Linas Nedzinskas ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Pilot Study ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Fracture Mechanics ◽  
Nuclear Power ◽  
Damage Mechanism ◽  
Core Damage ◽  
Steel Welds ◽  
Nuclear Power Plant Unit

A project with the acronym IRBIS (Ignalina Risk Based Inspection pilot Study) has been performed with the objective to perform a quantitative risk analysis of a total of 1240 stainless steel welds in Ignalina Nuclear Power Plant, unit 2 (INPP-2). The damage mechanism is IGSCC and the failure probabilities are quantified by using probabilistic fracture mechanics. The conditional core damage probabilities are taken from the plant PSA.

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