Advanced nuclear power plant regulation using risk-informed and performance-based methods

2009 ◽  
Vol 94 (2) ◽  
pp. 211-217 ◽  
Author(s):  
Mohammad Modarres
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
And Performance

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.

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

Research on Nuclear Power Plant Operational Safety Performance Based on Confidence Level and Fussy Evaluation Model

2013 ◽  
Vol 475-476 ◽  
pp. 1721-1724 ◽  
Author(s):  
Dong Xiao Niu ◽  
Zong Yun Song
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Performance Indicator ◽  
Evaluation Model ◽  
Indicator System ◽  
Safety Performance ◽  
Operational Safety ◽  
And Performance ◽  
Evaluation Matrix

Fussy evaluation model will be used in this article to evaluate the operational safety performance of nuclear power plant. Through the combination of the existing three indicator system, the article builds a safety performance indicator system and fatherly establishes evaluation matrix of the importance level and performance level,then gets the weigh and confidence of every indicator. Finally, the evaluation results of the operational safety performance of nuclear power plant can be obtained after analyzing the confidence and evaluation matrix.

The Impacts of Scale Effect on Flow Patterns in a Supersonic Steam Injector

2017 ◽  
Author(s):  
Masaya Fujishiro ◽  
Yutaka Abe ◽  
Akiko Kaneko
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Scale Effect ◽  
Flow Rate ◽  
Test Section ◽  
Nuclear Power ◽  
Flow Patterns ◽  
Water Jet ◽  
Steam Flow ◽  
And Performance

From the viewpoint of an importance of safety, the nuclear power plant should be managed to prepare severe accidents. The performance of safety dropped by an accident is strongly to be minimized during the situation of station blackout. The installation of a steam injector (SI) into the nuclear power plant has long been expected. In the SI, the steam condenses due to the direct contact at the surface of water jet, resulting in the force attracting water. The force drives the circulation of an amount of coolant water. SI also works as a reactor condenser thanks to its high efficient performance during the condensation. Because any external forces to circulate water and steam are not required, SI can be operated without the electric powers. The structure of SI is similar to a convergent-divergent nozzle. After the flow acceleration at a throat, the discharged pressure is expected to exceed the inlet pressure. Owing to its quite simple structure, the reduced cost of installation and maintenance is also expected. The following previous studies for four cases of throat diameter clarified two-phase flow structures and heat transfer characteristics in water jet and performance of SI: (i) Narabayashi et al. (2000) examined for 5.5 and 6.5 mm in diameter; (ii) Osakabe et al. (2004) for 3.4 mm; (iii) Koizumi et al. (2006) for 4 mm; (iv) Abe et al. (2014) for 4, 6.5, and 8 mm. Although these clarified the operative state which formed a water jet, operative condition was not elucidated. Furthermore, the scale effect for various diameters of SI has not been discussed in detail. The aim of this study is to clarify scale effect of a test section on operating criteria and performance. Experiment was performed to clarify the scale effect by using three types of throat diameters: 4, 6.5, and 8 mm. As a result, three formations of a water jet were observed: (i) formation, (ii) incomplete formation, and (iii) no formation. We proposed a classification which enables us to categorize complex flow patterns into five regimes. We clarified the operating criteria of them by comparing water flow rate with steam flow rate. SI did not form a water jet on the condition with low steam flow rate. The suppling water was stopped, and only steam was supplied to the test section for the condition that steam latent heat was larger than subcooled water enthalpy.

scholarly journals Demonstrating Structural Adequacy of Nuclear Power Plant Containment Structures for Beyond Design-Basis Pressure Loadings

2010 ◽  
Author(s):  
Joseph Braverman ◽  
Richard Morante ◽  
Charles Hofmayer ◽  
Robert Roche-Rivera ◽  
Jose Pires
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Structural Integrity ◽  
Nuclear Regulatory Commission ◽  
Gas Generation ◽  
Design Basis ◽  
And Performance ◽  
Regulatory Commission ◽  
Technical Basis

Demonstrating the structural integrity of U.S. nuclear power plant (NPP) containment structures, for beyond design-basis internal pressure loadings, is necessary to satisfy Nuclear Regulatory Commission (NRC) requirements and performance goals. This paper discusses methods for demonstrating the structural adequacy of the containment for beyond design-basis pressure loadings. Three distinct evaluations are addressed: (1) estimating the ultimate pressure capacity of the containment structure (10 CFR 50 [1] and US NRC Standard Review Plan, Section 3.8) [2]; (2) demonstrating the structural adequacy of the containment subjected to pressure loadings associated with combustible gas generation (10 CFR 52 [3] and 10 CFR 50 [1]); and (3) demonstrating the containment structural integrity for severe accidents (10 CFR 52 [3] as well as SECY 90–016 [4], SECY 93–087 [5], and related NRC staff requirements memoranda (SRMs)). The paper describes the technical basis for specific aspects of the methods presented. It also presents examples of past issues identified in licensing activities related to these evaluations.

Increasing Fatigue Strength and Wear Resistance of Additive Manufactured Nickel Alloy (UNS N07718) by Ultrasonic Nanocrystal Surface Modification (UNSM) Treatment

2020 ◽  
Author(s):  
Young Sik Pyun ◽  
Seimi Choi ◽  
Ruslan Karimbaev ◽  
Jun Suek Ro ◽  
Choong Ho Sanseong ◽  
...  
Keyword(s):  
Wear Resistance ◽  
Surface Modification ◽  
Fatigue Strength ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Wide Range ◽  
Direct Energy ◽  
Metal 3D Printing ◽  
And Performance

Abstract Additive Manufacturing (AM) which is also known as metal 3D printing technique is a promising process with a massive potential for developing a component for wide range applications for various industries. Recently, AM process was introduced to the nuclear power plant industry as AM is capable of manufacturing the substitution of aging and obsolete component. However, the AM component has inferior mechanical properties and performance in terms of fatigue strength and wear resistance compared to its conventionally manufactured counterpart. Ultrasonic Nanocrystal Surface Modification (UNSM) is one of mechanical surface modification treatment known for improving fatigue strength and wear resistance of wrought material. Hence, in this study effect of UNSM treatment on fatigue strength and wear resistance of additive manufactured material was investigated. The investigation was done to Ni-based alloy 718 (UNS N07718) as this material is used for nuclear power plant components and was manufactured with two different AM techniques namely Powder Bed Fusion (PBF) and Direct Energy Deposition (DED) processes. The evaluation was conducted by comparing the as-polished and UNSM-treated specimens for each AM processes by performing fatigue and tribo tests. This result will become a part of the technical basis for KEPIC Code Case development.

Sign in / Sign up

Export Citation Format

Share Document