scholarly journals HEAVY WATER ORGANIC COOLED REACTOR. 1000-Mwe NUCLEAR POWER PLANT PRELIMINARY CONCEPTUAL DESIGN. VOLUME II. PLANT DESCRIPTION

1965 ◽  
Author(s):  
2012 ◽  
Vol 2012 ◽  
pp. 1-17 ◽  
Author(s):  
Analia Bonelli ◽  
Oscar Mazzantini ◽  
Martin Sonnenkalb ◽  
Marcelo Caputo ◽  
Juan Matias García ◽  
...  

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.


1998 ◽  
Vol 120 (1) ◽  
pp. 93-98 ◽  
Author(s):  
G. R. Reddy ◽  
H. S. Kushwaha ◽  
S. C. Mahajan ◽  
K. Suzuki

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.


Author(s):  
Massimo Di Pietro ◽  
Sergio Pistelli ◽  
Eugenio Garneri ◽  
Rosa Lo Frano ◽  
Riccardo Ciolini

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.


2016 ◽  
Vol 92 ◽  
pp. 284-288 ◽  
Author(s):  
Hocheol Shin ◽  
Changhoi Kim ◽  
Yongchil Seo ◽  
Kyungmin Jeong ◽  
Youngsoo Choi ◽  
...  

2007 ◽  
Vol 2007 ◽  
pp. 1-9
Author(s):  
O. Mazzantini ◽  
J. C. Ferreri ◽  
F. D'Auria ◽  
C. P. Camusso

A systematic study of natural circulation (NC) in a postulated, varying primary mass inventory scenario at residual power fractions has been performed for a nuclear power plant operating in Argentina. It is a pressurized heavy water reactor, cooled and moderated by heavy water. The analysis seems particularly relevant at present, because a second nuclear power plant (NPP), of similar design and nearly 745 MWe, is now under finalization. NRC-RELAP5/MOD3.3 was the code used to perform the simulations. Results obtained are presented in the form of natural circulation flow maps. The trends obtained fit in the expected limits for integral test facilities representative of PWRs. In addition, the validity of a simplified analysis to scale single and two-phase core flow has been verified. A set of constants has been obtained, which permits predicting NC core mass flow rate (CMFR) for this NPP. Results are partially validated, for single-phase NC flow, using a documented plant transient, showing reasonable agreement. Also, the effect of pressurizer size on the predicted evolution curve in the NC flow map (NCFM) is discussed.


Author(s):  
Massimo Di Pietro ◽  
Sergio Pistelli ◽  
Eugenio Garneri ◽  
Rosa Lo Frano ◽  
Riccardo Ciolini

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 purifier pool of the Italian E. Fermi nuclear power plant (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 rate was found to have swarf suction. The feasibility of the method was demonstrated, even if it is required to homogenize the inlet mixture to avoid swarf packing conditions inside the ejector.


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