scholarly journals HEAVY WATER ORGANIC COOLED REACTOR. 1000-Mwe NUCLEAR POWER PLANT PRELIMINARY CONCEPTUAL DESIGN. VOLUME I. ECONOMIC ANALYSIS

1965 ◽  
Author(s):  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Economic Analysis ◽  
Conceptual Design ◽  
Heavy Water ◽  
Nuclear Power

Comprehensive techno-economic analysis of integrated nuclear power plant equipped with various hybrid desalination systems

Desalination ◽  
2020 ◽  
Vol 493 ◽  
pp. 114623 ◽  
Author(s):  
Khashayar Sadeghi ◽  
Seyed Hadi Ghazaie ◽  
Ekaterina Sokolova ◽  
Evgeniy Fedorovich ◽  
Amirsaeed Shirani
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Economic Analysis ◽  
Nuclear Power

scholarly journals Station Black-Out Analysis with MELCOR 1.8.6 Code for Atucha 2 Nuclear Power Plant

2012 ◽  
Vol 2012 ◽  
pp. 1-17 ◽  
Author(s):  
Analia Bonelli ◽  
Oscar Mazzantini ◽  
Martin Sonnenkalb ◽  
Marcelo Caputo ◽  
Juan Matias García ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Heavy Water ◽  
Nuclear Power ◽  
Failure Time ◽  
Thermal Power ◽  
Radiation Heat Transfer ◽  
Primary System ◽  
Water Release ◽  
Plant Safety

A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

Decoupling Criteria for Multi-Connected Equipment

1998 ◽  
Vol 120 (1) ◽  
pp. 93-98 ◽  
Author(s):  
G. R. Reddy ◽  
H. S. Kushwaha ◽  
S. C. Mahajan ◽  
K. Suzuki
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Internal Structure ◽  
Heavy Water ◽  
Nuclear Power ◽  
Seismic Analysis ◽  
Real Life ◽  
Water Reactor ◽  
Reactor Building ◽  
Heavy Water Reactor

Generally, for the seismic analysis of nuclear power plant structures, requirement of coupling equipment is checked by applying USNRC decoupling criteria. This criteria is developed for the equipment connected to the structure at one location. In this paper, limitations of this criteria and modifications required for application to real life structures such as pressurized heavy water reactor building are discussed. In addition, the authors endeavor to present a decoupling model for multi-connected structure-equipment. The applicability of the model is demonstrated with pressurized heavy water reactor building internal structure and steam generator.

Handling and Conditioning Techniques of Activated Chips for the Decommissioning of the E. Fermi Nuclear Power Plant

2016 ◽  
Author(s):  
Massimo Di Pietro ◽  
Sergio Pistelli ◽  
Eugenio Garneri ◽  
Rosa Lo Frano ◽  
Riccardo Ciolini
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Conceptual Design ◽  
Nuclear Power ◽  
New Technique ◽  
Liquid Matrix ◽  
Radioactive Materials ◽  
Inlet Flow ◽  
Know How ◽  
A New Technique

In this paper a new technique to handle solid radioactive materials inside a liquid matrix is presented. The conceptual design of the device profits of the experience and know-how gained in decontamination procedures. The proposed system makes use of an ejector for the suction of a water-highly radioactive swarf mixture from the purifiers pool of the Italian E. Fermi NPP and moving it in a suitable container for the subsequent conditioning. A dedicated circuit with an ejector to demonstrate the feasibility of the method was realized. A minimum inlet flow was found to have swarf suction. No swarf packaging conditions were observed in the performed tests, demonstrating the feasibility of the method.

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