scholarly journals Study on life cycle management system for chillers in nuclear power plant

2018 ◽  
Vol 1074 ◽  
pp. 012153
Author(s):  
Jie Yang ◽  
Liang Yuan ◽  
Lin Su ◽  
Qiang Qin ◽  
Rudong Wang
Keyword(s):  
Life Cycle ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Management System ◽  
Nuclear Power ◽  
Life Cycle Management

scholarly journals Study on Life Cycle Management System for Main condensers in Nuclear Power Plant

2021 ◽  
Vol 252 ◽  
pp. 02075
Author(s):  
Yang Jie ◽  
Yuan Liang ◽  
Yang Wu ◽  
Qin Qiang
Keyword(s):  
Life Cycle ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Management System ◽  
Nuclear Power ◽  
Management Practices ◽  
Life Cycle Management ◽  
Daya Bay ◽  
Commercial Operation

Daya Bay Nuclear Power Plant has been running for above 20 years. main condensers have begun to run during the commissioning phase before the official commercial operation, so it is imminent to carry out the life cycle management of main condensers combined with demonstration of the operation license extended to 60 years. A life cycle management system for main condensers in nuclear power plant is established in this paper, which is applied to management practices of Daya Bay Nuclear Power Plant.

scholarly journals Life Cycle Assessment of the New Generation GT-MHR Nuclear Power Plant

Energies ◽  
2018 ◽  
Vol 11 (12) ◽  
pp. 3452 ◽  
Author(s):  
Paul Koltun ◽  
Alfred Tsykalo ◽  
Vasily Novozhilov
Keyword(s):  
Life Cycle Assessment ◽  
Life Cycle ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Greenhouse Gases ◽  
Nuclear Power ◽  
Energy Intensity ◽  
Ghg Emissions ◽  
Electricity Production ◽  
Hybrid Lca

This study describes a life cycle assessment (LCA) of a fourth generation (4G) nuclear power plant. A high temperature helium cooled reactor and gas turbine technology with modular helium reactor (GT-MHR) is used in this study as an example. This is currently one the safest design of a nuclear power plant. The study also takes into account impact of accidents and incidents (AI) which happened around the world at nuclear power generation facilities. The adopted method for the study is a hybrid LCA analysis. The analysis of each phase of the life cycle was done on the basis of process chain analysis (PCA). Where detailed data were not available, the Input/Output (I/O) databases was employed. The obtained results show that greenhouse gases (GHG) emissions and energy intensity per unit of electricity production are relatively low. In fact, these are even lower than emissions from a number of renewable energy sources. The results show considerably different greenhouse gases (GHG) emissions and energy intensity per unit of electricity production when effects of AI are taken into account.

Developing and Implementing Ai-Based Classifier for Requirements Engineering

2021 ◽  
Author(s):  
Santeri Myllynen ◽  
Ilpo Suominen ◽  
Tapani Raunio ◽  
Rasmus Karell ◽  
Jussi Lahtinen
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Requirements Engineering ◽  
Language Processing ◽  
Management System ◽  
Nuclear Power ◽  
Requirements Management ◽  
Related System ◽  
Data Comparison

Abstract In nuclear power plant projects, requirements engineering manages the sheer volume of requirements, typically characterized by descriptive and non-harmonized requirements. Large projects may have tens of thousands to hundreds of thousands of requirements to be managed and fulfilled. There are two main issues impeding requirements analysis; tortuous requirements to be interpreted, and humans' very limited ability to concentrate on a specific task. Therefore, it has been recognized that artificial intelligence (AI) algorithms could have potential to support designers' decision-making in classifying and allocating nuclear power plant requirements. This paper presents our work on developing an AI-based requirements classifier utilizing natural language processing (NLP) and its integration with the requirements management system. The focus is on the classification of nuclear power industry-specific requirements utilizing deep learning-based NLP. Three classifiers are compared with each other and the corresponding results are presented. The results include predetermined requirement classes, manually gathered and classified data, comparison of three models and their classification accuracies, microservice system architecture and integration of the established classifier with the requirements management system. As the performance of the requirements classifier and related system has been successfully demonstrated, future AI-specific development and studies are suggested to focus on atomizing multi-class requirements, combining similar requirements into one, checking requirements syntax and utilizing unsupervised learning for clustering. Furthermore, new and advantageous requirement classes and hierarchies are suggested to be developed while also improving current datasets both quantitatively and qualitatively.

Developing Software Configuration Management System for Digital Instrumentation and Control (DI&C) System of Nuclear Power Plant

2010 ◽  
Author(s):  
I-Hsin Chou ◽  
Hsueh-Wei Hsiao ◽  
Che-An Chang
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Management System ◽  
Nuclear Power ◽  
Configuration Management ◽  
Software Configuration Management ◽  
Software Products ◽  
Software Configuration ◽  
Digital Instrumentation ◽  
And Control

As Nuclear Power Plant (NPP) adopted software-based Digital Instrumentation and Control (DI&C) System, the Software Configuration Management (SCM) is becoming more and more important for NPP. The main reason is the inherent changeability and invisibility which of software often causes unpredictable problems and results are difficult to manage. In addition, the DI&C system has always been constructed by multiple vendors and each vendor of the DI&C has its own development artifacts. Therefore, it is great challenge for NPP staff to maintain the consistency and integrity of software Configuration Items (CI) among multiple vendors. The software CIs include software products delivered to customers and items required to create the software products such as software design document, source code, database, test report, compiler, etc. In general, Software Configuration Management System (SCMS) is usually developed to support SCM activities, such as storing CI, controlling change, and accounting and auditing throughout the entire software lifecycle. However, most existing file-based SCMS typically deal with those artifacts of individual files without providing the more detailed configuration and change information among CIs. Based on the nuclear SCM related regulations, this paper proposes a developing SCMS for the DI&C system of a NPP. Its main goal is to meet the regulatory requirements, and enhance the visibility, tractability and integrate ability to manage the heterogeneous subsystems within the DI&C system. This paper provides the more detailed descriptions about regulation requirements analysis, system design and the development process. Finally, a prototype system is presented.

Fangjiashan Nuclear Power Plant Unit1 Fuel Handling and Storage System (PMC) V&V Overview

2013 ◽  
Author(s):  
Gang Ma
Keyword(s):  
Life Cycle ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Systems Engineering ◽  
Nuclear Power ◽  
Objective Assessment ◽  
Storage System ◽  
Nuclear Industry ◽  
Expert Committee ◽  
And Storage

The product of Fangjiashan Nuclear Power Plant (NPP) Unit1 Fuel Handling and Storage (PMC) System is the first Chinese PMC system, with its own intellectual property rights. During the development and design lifecycle for the product, China Nuclear Control System Engineering Co., Ltd (CNCS) was responsible for Verification and Validation (V&V) processes of the PMC system, taking a significant role for ensuring the reliability and safety of the software in PMC system. The PMC V&V project is also the first ever independent V&V project of the China nuclear industry. V&V is a technical discipline of systems engineering. The purpose of V&V is to help the development team build quality into the system during the life cycle. The V&V processes determine whether the product developed satisfies its intended use and user’s needs. V&V provides an objective assessment of products and processes throughout the life cycle. This assessment demonstrates whether the requirements are correct, complete, accurate, consistent, and testable. CNCS V&V PMC project team performed PMC V&V activities in compliance with IEEE Std 1012-1998, which is endorsed by NRC Regulatory Guide 1.168-2004. After critical analyses by V&V team, the Software Integrity Level (SIL) of PMC is SIL3, so associated V&V activities must conform to the minimum tasks list in IEEE Std 1012-1998 Table 1. After 2 years of hard working, Fangjiashan NPP Unit1 PMC system V&V activities have been completed. The whole activities and methodology was passed the final evaluation by the customer and was highly compliment by the international V&V expert committee at year of 2012. This paper discusses how to establish V&V organization and infrastructure, and then how to perform V&V activities in high quality, and the specific new and best practice methods, approach and tools for executing V&V tasks. Because the PMC V&V project is the first ever independent V&V project of the China nuclear industry, the methods, approach and tools which was executed in the whole lifecycle and depicted in this paper could help to guide and be referred by the future V&V activities and projects.

Sign in / Sign up

Export Citation Format

Share Document