Nuclear Engineering International

World Nuclear Industy Handbook 1993 (aimual issuance). Nuclear Engineering International, Sutton, Surrey, U.K. 

D149795, Nuclear Engineering International, 1995 D149875, Charles, 1996 D17884B, Vargo, 1997... 

Bmschi, H. and T. Andersen Turning the Key, Nuclear Engineering International, 1 (November 1991). 

Fuel Cycle Review 1990, Nuclear Engineering International. 

Fabian, T. (2004) US utilities claim billions, Nuclear Engineering International, July 2004. 

Nuclear Engineering International, Quadrant Services, Haywards Heath, UK... 

Nuclear Engineering International, Wilmington Publ. Co, Wilmington, UK (Vol. 46, 2001). Nuclear Science and Engineering, Am. Nucl. Soc., La Grange Park, Illinois (Vol. 137, 2001) Nuclear Technology, Am. Nucl. Soc., La Grange Park, Illinois (Vol. 133, 2001). 

World Nuclear Industry Handbook - 2(XX), Nuclear Engineering International, ISBN 1903077176, 2000. 

Perera J. (2002). Waste control and management in Moscow. Nuclear Engineering International 47(581) 39-41. 

F. E. Taylor, HMNII View of the Licensee as an Intelligent Customer, draft paper for submission to Nuclear Engineering International, dated January 2000. 

Nuclear Engineering International (1999), 1999 World Nuclear Industry Handbook, Wilmington, United Kingdom, Wilmington Publishing. 

A. Ballesteros, I. Marcelles and J. Bros, Beyond RPV design hfe. Nuclear Engineering International, 48, 2003,32. 

D. Fishlock, Once and for all Rolls-Royce is close to the all-life core. Nuclear Engineering International, 1994 April, pp. 34-36. 

Source OECD/NEA. 2004. Nuclear energy data. Nuclear engineering. International Handbook. http // www.world-nuclear.org/info/inf69.html. 

ANDERSON, C. K. Interim Spent Fuel Management 1995 Update, Nuclear Engineering International (March 1995)... 

POPLAVSKY, V.M., et al., BN-1800 a next generation fast breeder. Nuclear Engineering International, June 2004. 

Green, R. (2003). Back to the future. Nuclear Engineering International, pp. 36-39, September. 

XX-20] GREENSPAN, E., et al.. The encapsulated nuclear heat-source (ENHS) reactor. Summary Report of U year of NERI Project No. 990154 Feasibility Study, University of Califomia-Berkeley Nuclear Engineering Internal Report... 

Measures for fire protection at Neckar Nuclear Power Plant (Wiechers, R., in Fire Safety 94, Nuclear Engineering International, ISBN 0617005583, December 1994). 

Gimstedt, Haga, I., Wassberg, R., and Nilsson, L. B. Articles on Oskarshamn 1 Nuclear Power Station. Nuclear Engineering International. 1970. 

Burrow, R. E. D. and WILLIAMS, A. J. Hartlepool advanced gas-cooled reactor— reactor pressure vessel. Nuclear Engineering International. Vol. 14, No. 162, 1969. 

Business Press International. 2010. World Nuclear Industry Handbook. Sutton, Surrey, U.K. Business Press International. Issued as a supplement to the Novanber issue of Nuclear Engineering International, this publication provides up-to-date contact information as well as products and services information. 

Nuclear Engineering International. 1968- Londou Heywood-Temple Industrial Publications. Continues Nuclear Eugiueeriug (London) (0029-5507). 

Nuclear Engineering International, 21, 246, 39 (1976), SNR-300, Liquid Metal Fast Breeder Reactor Prototype Plant. 

Building Monju - Japan s Prototype FBR", Nuclear Engineering International, October, 1991. 

Robin, M. G., Careful Attention to Detail was Necessary in Developing the SUPER-PHENIX Steam Generators. Nuclear Engineering International, 22 May, 1977,46. 

Fig. 8.3. Coolant circulation system for Hartlepool advanced gas-cooled reactor (courtesy of Nuclear Engineering International).

Fig. 8.5. Coolant circulation system for Fort St. Vrain high-temperature gas-cooled reactor (courtesy of General Atomic Company and Nuclear Engineering International). A, Fueling penetrations B, control rods C, orifice valves D, reflector E, reactor core F, core floor G, hot helium H, cold helium J, pressurized concrete reactor vessel K, steam generator L, helium circulator.

Fig. 9.3. Sectional view of the Sequoyah pressurized water reactor (courtesy of Nuclear Engineering International). A, Control rod drive head adaptors B, instrumentation ports C, thermal sleeves D, upper support plate E, support column F, control rod drive shaft G, control rod guide tube H, internals support ledge J, inlet nozzle K, outlet nozzle L, upper core plate M, baffle and former N, fuel assemblies O, reactor vessel P, thermal shield Q, access port R, lower core plate S, core support T, diffuser plate U, lower support column V, radial supports W, instrumentation thimble guides.

Fig. 9.6, Sectional view of the Grand Gulf boiling water reactor (courtesy of General Electric Company and Nuclear Engineering International). A, Vent and head spray B, steam dryer C, steam outlet D, core spray outlet E, steam separators F, feedwater inlet G, feedwater sparger H, L.P. coolant injection inlet J, core spray pipe K, core spray sparger L, top guide M, jet pump N, core shroud O, fuel assemblies P, control blade Q, core plate R, jet pump water inlet S, recirculation water outlet T, vessel support skirt U, control rod drives V, in-core flux monitor.

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