Reactor Experimental Boiling Water

The EBWR Experimental Boiling Water Reactor, ANL-5607, Argonne National Laboratory, U.S. Atomic Energy Commission, Washington, D.C., 1957. 

To achieve higher thermal efficiency, nuclear steam reheat has to be introduced inside a reactor. Currently, aU supercritical turbines at thermal power plants have a steam reheat option. In the 1960s and 1970s, Russia, the US, and some other countries have developed and implemented nuclear steam reheat at subcritical pressures in experimental reactors. Therefore, it is important to summarize the worldwide expmence of implementing nuclear steam reheat at several experimental boiling water reactors (BWRs) and utilize it in the context of development of SCWRs concepts with a steam reheat option. 

The Plutonium Recycle Program concentrated mainly on mixed oxide fuels (uranium and plutonium) however, some efforts were devoted to the fabrication and testing of zircaloy-cladded, plutonium-aluminum fuels in the Plutonium Recycle Test Reactor and the Experimental Boiling Water Reactor at the INEL. 

United States of America Murphie, W.E. US Department of Energy Office of Enviromnental Restoration and Waste Management Decommissioning of the experimental boiling water reactor pressure vessel... 

THE STATUS OF THE EXPERIMENTAL BOILING WATER REACTOR (EBWR) DECONTAMINATION AND DECOMMISSIONING PROJECT... 

ARGONNE NATIONAL LABORATORY, "The EBWR experimental boiling water reactor", AML 5607, (1957). 

Development of the boiling water reactor (BWR) was carried out by the ANL. Following the operation of several experimental reactors in Idaho, the experimental BWR (EBWR) was constructed in Illinois. The EBWR was the first BWR power plant to be built. The plant was initially operated at 5 Megawatts electric (MWe) and 20 Megawatts thermal (MWt). The reactor was operated from 1957 to 1967 at power levels up to 100 MWt. 

Marcel, C.P., 2007. Experimental and Numerical Stabihty Investigations on Natural Circulation Boiling Water Reactors (Doctoral thesis). Delft University of Technology. 

DE KRUUF, W J M, VAN DER HAGEN, T.H.J.J., ZBORAY, R., MANERA, A, MUDDE, R.F., CIRCUS and DESIRE Experimental Facilities for Research on Natural-Circulation Cooled Boiling Water Reactors , this publication. 

CIRCUS and DESIRE experimental facilities for research on natural-circulation-cooled boiling water reactors... 

The same plasma polymer deposited in a closed-system reactor has a graded elemental composition with a carbon-rich top surface, and the oligomer content is much lower [10], both of which increase the level of adhesion. The adhesion of the same water-borne primer is excellent and survives 8 h immersion in boiling water. When this surface is treated with O2 plasma, the adhesion does not survive 1 h of boiling, while the dry tape test still remains at the level of 5. The water-sensitivity of adhesion depends on the chemical nature of the top surface as depicted by XPS data shown in Figure 28.12. Water-insensitive tenacious adhesion, coupled with good transport barrier characteristics, provides excellent corrosion protection, as supported by experimental data [1-4], and constitutes the basic principle for the barrier-adhesion approach. 

An experimental program was carried out in the Czech Republic, where Boiling crisis and Critical Heat Flux (CHF) were measured on the facilities that simulated the fuel assemblies of the former Soviet s Pressurised Water Reactors (PWR) WWER-440 and WWER-1000. The large part of experiments related to the CHF was performed at Skoda Plzen Ltd, Nuclear Machinery Plant. The NRI started a complex of research activities in this field at the end of seventies. 

XXV-8] TAKAHASHI, M., et al., Design and experimental study for development of Pb-Bi cooled direct contact boiling water small fast reactor (PBWFR), ICAPP 04 (Proc. Int. Congress, Pittsburgh, PA, USA, June 2004). 

The Elk River, BWR, located about 30 miles northwest of Mirmeapohs, was anoflier experimental project mislabeled as demonstration (Anon., 1961). It was intended to combine an indirect boiling water natural circulation reactor with a fossil fuel powered superheater. Specifically, the water boiling inside the core was sent to an external heat... 

The second important component is the cooling agent or reactor coolant which extracts the heat of fission for some usefiil purpose and prevents melting of the reactor materials. The most common coolant is ordinary water at high temperature and high pressure to limit the extent of boiling. Other coolants that have been used are Hquid sodium, sodium—potassium alloy, helium, air, and carbon dioxide (qv). Surface cooling by air is limited to unreflected test reactors or experimental reactors operated at very low power. 

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