**7. References**


**Acknowledgement** 

**7. References** 

Conference.

497-504

9, 309-326

data analysis of the orifice case study.

Vol. 119, pp. 431-438.

Vol. 221, no. 2, pp. 77-88.

The support provided by the Deanship of Scientific Research (DSR) at King Fahd University of Petroleum & Minerals (KFUPM) for funding this research work through project No. IN090038, is gratefully acknowledged. The author also thanks Mr. Mufatiu Bello for carrying out the

Also, the author would like to thank Atomic Energy of Canada Ltd. (AECL), and the CANDU Owner Group (COG) for their support and permission to publish the data on plant close-proximity effect presented in this chapter. The data have been also presented by the

[1] Kanster, W., Erve, M., Henzel, N., and Stellwag, B., (1990), "Calculation code for erosion corrosion induced wall thinning in piping system, Nuclear Engineering and Design,

[2] Yurmanov, V., Rakhmanov, A., (2009), "Workshop on erosion-corrosion, International Atomic Energy Agency, Workshop on Erosion-Corrosion, Moscow, Russian Federation. [3] Moore, F.E., (2008), "Welding and repair technology for power plants, 18th Int. EPRI

[4] Ahmed, W.H. (2010), "Evaluation of the proximity effect on flow accelerated corrosion",

[5] Crawford, N.M., Cunningham, G., Spence, S.W.T. (2007), "An experimental investigation into the pressure drop for turbulent flow in 90° elbow bends" Proc. of the Institution of Mechanical Engineers, Part E, Journal of Process Mechanical Engineering,

[6] Poulson B. (1999), "Complexities in predicting erosion corrosion", Wear 233-235, pp.

[7] Chen X, McLaury B.S., Shirazi S. A.,, (2006), "A Comprehensive Procedure to Estimate Erosion in Elbows for Gas/Liquid/Sand Multiphase Flow " ASME Journal of Energy

[8] Kim S., Park J.H., Kojasoy G., Kelly J.M., Marshall S.O. (2007), "Geometric effects of 90 degree Elbow in the development of interfacial structures in horizontal bubbly flow ",

[9] Hassan YA, Schmidl W., Ortiz-Villafuerte J. (1998), "Investigation of three-dimensional two-phase flow structure in a bubbly pipe flow" Measurement Science Technology, Vol.

[10] Jepson, W. P., (1989), " Modelling the transition to slug flow in horizontal conduit",

[11] Keating, A., and Nesic, S., (1999 ), " Prediction of two-phase erosion-corrosion in bends", Second International Conference on CFD in the Mineral and Process Industries,

author and analyzed in the Annals of Nuclear Energy (37 (2010) 598–605)

Annals of Nuclear Energy, Vol. 37, pp. 598-605.

Resources Technology, Vol. 128, pp. 70-78.

CSIRO, Melbourne, Australia, Dec. 6-8.

Nuclear Engineering and Design, Vol.237, 2105-2113

Canadian Journal of Chemical Engineering, Vol. 67, pp. 731-740


[29] Poulson, B. (2007), Proc. of 13th Int. Conf. On Environmental Degradation of Materials in Nuclear Power Systems- Canadian Nuclear Soc, Whistler, B.C., Canada.

**Chapter 7** 

© 2012 Kotov, licensee InTech. This is an open access chapter distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/3.0), which permits unrestricted use,

distribution, and reproduction in any medium, provided the original work is properly cited.

© 2012 Kotov, licensee InTech. This is a paper distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/3.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

**Thermal Reactors with High Reproduction of** 

Efficiency of power reactors is determined by the expenses of raw material for its work and

In general modern nuclear power plants (NPP) use thermal reactors with enriched by isotope 235U uranium (comparing to raw uranium) in the beginning of campaign. This fuel allows having sufficient reactivity margin for obtaining burn-up more than 30-50 MW\*day/kg. This reactor type is developed by itself during short period of nuclear power plants development. Raw uranium cannot supply required burn-up even in reactors with best heavy-water moderator. An effective technology of isotope separation was made for

Known shortage of thermal reactors is small usage of raw uranium during its work (0.5 – 1.0 %). Stocks of cheap ore for these reactors are enough for 40-50 years at power level of 4000

The next step in nuclear power plants development is suggested usage of fast neutron reactors. This transition is connected with fuel enrichment increase and it supplies possibility of fission reactions on fast neutrons, which produce more secondary neutrons. By solving technical problems at this direction, nuclear power plants supplied with cheap enough fuel for many centuries can be built. But this development direction has one

When it`s advocates say that high price is because of modern technical solutions shortages, they are half right. Insuperable high price is because of high raw uranium requirement for its start. For using nuclear power plants with total power of 4000 GW, which are supplied for 3000 years, all cheap uranium stocks must be processed in 40-50 years [2]. It is connected with ecological problems and some complexity in non-proliferation of nuclear fission materials.

**Fission Materials** 

Additional information is available at the end of the chapter

by efficiency of heat to mechanical energy transformation.

Vladimir M. Kotov

**1. Introduction** 

military purposes.

shortage. It is extremely expensive.

GW [1].

http://dx.doi.org/10.5772/51599
