scholarly journals Design data and safety features of commercial nuclear power plants. Vol. III. Docket No. 50-397 through 50-449

1974 ◽  
Author(s):  
F. A. Heddleson
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Design Data ◽  
Safety Features

Performance Simulation to Understand the Effects of Multifluid Scaling of Gas Turbine Components for Generation IV Nuclear Power Plants

2020 ◽  
Vol 6 (2) ◽  
Author(s):  
Emmanuel O. Osigwe ◽  
Arnold Gad-Briggs ◽  
Theoklis Nikolaidis ◽  
Pericles Pilidis ◽  
Suresh Sampath
Keyword(s):  
Gas Turbine ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Design Data ◽  
Performance Simulation ◽  
Working Fluids ◽  
Simulation Tools ◽  
Component Map ◽  
Very High

Abstract A significant hurdle in the development of performance simulation tools to analyze and evaluate nuclear power plants (NPP) is finding data relating to component performance maps. As a result, engineers often rely on an estimation approach using various scaling techniques. The purpose of this study is to determine the component characteristics of a closed-cycle gas turbine NPP using the existing component maps with the corresponding design data. The design data are applied for different working fluids using a multifluid scaling approach to adapt data from one component map into another. The multifluid scaling technique described herein was developed as an in-house computer simulation tool. This approach makes it easy to theoretically scale the existing maps using similar or different working fluids without carrying out a full experimental test or repeating the whole design and development process. The results of selected case studies show a reasonable agreement with the available data. The analyses intend to aid the development of cycles for Generation IV NPPs specifically gas-cooled fast reactors (GFRs) and very high-temperature reactors (VHTRs).

scholarly journals Safety features in nuclear power plants to eliminate the need of emergency planning in public domain

Sadhana ◽  
2013 ◽  
Vol 38 (5) ◽  
pp. 925-943 ◽  
Author(s):  
P K VIJAYAN ◽  
M T KAMBLE ◽  
A K NAYAK ◽  
K K VAZE ◽  
R K SINHA
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Public Domain ◽  
Emergency Planning ◽  
Safety Features

A new design concept for offshore nuclear power plants with enhanced safety features

2013 ◽  
Vol 254 ◽  
pp. 129-141 ◽  
Author(s):  
Kihwan Lee ◽  
Kang-Heon Lee ◽  
Jeong Ik Lee ◽  
Yong Hoon Jeong ◽  
Phill-Seung Lee
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Design Concept ◽  
Safety Features

Hazard Analysis of Digital Engineered Safety Features Actuation System in Advanced Nuclear Power Plants Using a Redundancy-Guided Approach

2020 ◽  
Author(s):  
Han Bao ◽  
Tate Shorthill ◽  
Hongbin Zhang
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Hazard Analysis ◽  
Potential Threat ◽  
Safety Control ◽  
Application Systems ◽  
Actuation System ◽  
Safety Features ◽  
Safety Systems

Abstract Replacing the existing aging analog instrumentation and control (I&C) systems with modern safety control and protection digital technology offers one of the foremost means of performance improvements and cost reductions for the existing nuclear power plants (NPPs). However, the qualification of digital I&C systems remains a challenge, especially considering the issue of software common-cause failures (CCFs), which are difficult to address. With the application and upgrades of advanced digital I&C systems, software CCFs have become a potential threat to plant safety because most redundant designs use similar digital platforms or software in the operating and application systems. With complex designs of multilayer redundancy to meet the single-failure criterion, digital I&C safety systems (e.g., engineered safety-features actuation system [ESFAS]) are of a particular concern in the U.S. Nuclear Regulatory Commission (NRC) licensing procedures. This paper applies a modularized approach to conduct redundancy-guided systems-theoretic hazard analysis for an advanced digital ESFAS with multilevel redundancy designs. Systematic methods and risk-informed tools are incorporated to address both hardware and software CCFs, which provide guidance to eliminate the triggers of potential single points of failure in the design of digital safety systems in advanced plant designs.

Work structure in nuclear power plants

1983 ◽  
Author(s):  
Marjorie B. Bauman ◽  
Richard F. Pain ◽  
Harold P. Van Cott ◽  
Margery K. Davidson
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Work Structure
Sign in / Sign up

Export Citation Format

Share Document