Imperfect Maintenance Scheduling for High Pressure Feedwater Heater System in Nuclear Power Plant

2020 ◽  
Author(s):  
Mengyu Du ◽  
Chen Zhang ◽  
Taotao Zhou ◽  
Yan-Fu Li
Keyword(s):  
High Pressure ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Maintenance Scheduling ◽  
Imperfect Maintenance

scholarly journals Neutronic safety analysis of proposed reactor technologies for Ghana’s nuclear power plant using the MCNP code

2019 ◽  
Vol 34 (3) ◽  
pp. 238-242
Author(s):  
Rex Abrefah ◽  
Prince Atsu ◽  
Robert Sogbadji
Keyword(s):  
High Pressure ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Atomic Energy Commission ◽  
Clean Energy ◽  
Safety Analysis ◽  
Operating Conditions ◽  
The Government

In pursuance of sufficient, stable and clean energy to solve the ever-looming power crisis in Ghana, the Nuclear Power Institute of the Ghana Atomic Energy Commission has on the agenda to advise the government on the nuclear power to include in the country's energy mix. After consideration of several proposed nuclear reactor technologies, the Nuclear Power Institute considered a high pressure reactor or vodo-vodyanoi energetichesky reactor as the nuclear power technologies for Ghana's first nuclear power plant. As part of technology assessments, neutronic safety parameters of both reactors are investigated. The MCNP neutronic code was employed as a computational tool to analyze the reactivity temperature coefficients, moderator void coefficient, criticality and neutron behavior at various operating conditions. The high pressure reactor which is still under construction and theoretical safety analysis, showed good inherent safety features which are comparable to the already existing European pressurized reactor technology.

Temperature oscillation in a high-pressure regeneration system of a nuclear power plant with a VVÉR-1000 reactor

Atomic Energy ◽  
1994 ◽  
Vol 76 (2) ◽  
pp. 86-90
Author(s):  
V. I. Baranenko ◽  
V. S. Kirov ◽  
V. P. Kravchenko ◽  
V. A. Korovkin ◽  
N. A. Fridman
Keyword(s):  
High Pressure ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Temperature Oscillation ◽  
Regeneration System

Verification and Validation of CFD Model to Predict Jet Loads and Blast Wave Pressures From High Pressure Superheated Steam Line Break

2016 ◽  
Author(s):  
S. Pal ◽  
C. Iek ◽  
L. J. Peltier ◽  
A. Smirnov ◽  
K. J. Knight ◽  
...  
Keyword(s):  
High Pressure ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Blast Wave ◽  
Nuclear Power ◽  
Steam Line ◽  
Blast Waves ◽  
Verification And Validation ◽  
Jet Flows ◽  
Cfd Model

High pressure superheated or saturated steam line breaks in a nuclear power plant generate high speed jet flows and blast waves. The jet loads and blast wave pressures can damage critical nuclear power plant components. An accurate assessment of these effects including uncertainty quantification (UQ), is essential to confirm that design is robust enough to handle jet flows and blast waves from postulated steam line breaks. This paper presents the verification and validation of a computational model created using a commercial CFD code for making such assessments. The verification and validation process involves the steps of application space parametrization, Phenomena Identification and Ranking (PIR), CFD model lockdown, selection of validation dataset, and calculation of formal validation metrics. The Uncertainty Quantification in the actual application should include the propagated validation uncertainties from the validation test problems.

The Application of Risk-Informed Decision-Making Approach in Optimization of Allowed Outage Time for Safety System in Nuclear Power Plant

2017 ◽  
Author(s):  
Licun Wu ◽  
Chao Ma ◽  
Wei Deng
Keyword(s):  
Decision Making ◽  
High Pressure ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Safety System ◽  
Informed Decision ◽  
Informed Decision Making ◽  
Deterministic Analysis ◽  
The Impact

To facilitate online maintenance for High Pressure Safety Injection (HPSI) system in nuclear power plant, the optimization measure for Allowed Outage Time (AOT) is proposed in this paper, and risk-Informed decision-making approach is used to demonstrate its feasibility. According to the analysis results, the extension of AOT meets the requirements of relative guides and deterministic analysis, and the impact on risk of plant is acceptable. Based on the extension of AOT, it is feasible to carry out online maintenance for safety system and corresponding support systems, which can effectively reduce workload during shutdown.

Evaluation Study of NPPs Design Improvement Based on SGTR Calculation Result

2013 ◽  
Author(s):  
Jian Zhang ◽  
Changjiang Yang
Keyword(s):  
High Pressure ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Calculation Result ◽  
Nuclear Power ◽  
Evaluation Study ◽  
Design Improvement ◽  
2Nd Generation ◽  
Fast Cooling ◽  
The Impact

CP1000, improved from 2nd generation nuclear power plant technology, is a new concept of 2nd plus technology, some improvements of which are relatively mature. Based on the technology of 2nd plus, two new design improvements are being implemented, substituting high pressure safety injection with middle pressure safety injection and adding a function of fast cooling when an accident happens. Using code RELAP5, this article calculated and analyzed SGTR accident in order to evaluate the impact of the two improvements.

Sign in / Sign up

Export Citation Format

Share Document