Safety Preventive Maintenance in Nuclear Power Plant
R.Mohan1, N.Partheeban2
1R.Mohan, Department of PG Computer Science & Engg, S.A. Engineering College, Chennai (Tamil Nadu), India.
2Dr. N. Partheeban, Associate Professor, Department of IT, S.A. Engineering College, Chennai (Tamil Nadu), India.
Manuscript received on 18 June 2012 | Revised Manuscript received on 25 June 2012 | Manuscript published on 30 June 2012 | PP: 209-215 | Volume-1 Issue-2, June 2012 | Retrieval Number: B0239051212/2012©BEIESP
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© The Authors. Blue Eyes Intelligence Engineering and Sciences Publication (BEIESP). This is an open access article under the CC-BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/)
Abstract: Safety analysis of a nuclear power plant for postulated initiating events (PIEs) is an essential part of the design process, both as a regulatory requirement and also to generate performance requirement of safety system. A wide variety of computer codes have been developed in-house at Nuclear Power Corporation of India Limited (NPCIL) for safety analysis of Indian Pressurized Heavy Water Reactors (PHWRs). The applications and validation of these codes are discussed in this article. In addition to the conventional ‘deterministic’ safety analysis approaches, probabilistic safety assessment (PSA) techniques are also being applied in Indian PHWRs to gain additional insights Passing of steam trap becomes a major concern for all power plants due to highenthalpy energy loss as well as wastage of costly DM water. On the other hand, if steam trap does not do its intended function, then it may lead to the damage of turbine and pipelines. Unfortunately, most power plants do not have a proper condition monitoring or preventive maintenance programmed for steam trap to know its healthiness.
Keywords: Nuclear Energy, Thermal Hydraulic, Stream Trap. Thermo dynamic, Radioactive Waste.
Scope of the Article: Low-power Design