Fast reactor engineering

Lee, D. H., 1970, Studies of Heat Transfer and Pressure Drop Relevant to Subcritical Once-through Evaporator, Paper IAEA-SM-130/56, Symp. on Progress in Sodium-Cooled Fast Reactor Engineering, Monte Carlo, Monaco. (4)... 

Shirin, V. M., et al. Use of Lead in Unloading Systems of Sodium-Cooled Facilities, in IAEA Symposium on Progress in Sodium-Cooled Fast Reactor Engineering, Monaco, Mar. 1970. 

FAST REACTOR ENGINEERING 6.5.1. Sodium-water interaction... 

The 65 MW(th)/25 MW(e) China experimental fast reactor (CEFR) is under construction. This is the first step in the Chinese fast reactor engineering development. 

TAYLOR, D., Prototype fast reactor heat-transport system, paper presented in the IAEA Simp, on Sodium-cooled fast reactor engineering, 23-27 March 1970, Monaco. 

The present status report intends to provide comprehensive and detailed information on LMFR technology. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors, on the following topics experience in constmction and operation, reactor physics and safety, core structural material and fuel technology, fast reactor engineering and activities in progress on LMFR plants. 

Chemical reactions will take place only when the reactant molecules are in intimate contact. In some cases, especially with very fast reactions or viscous liquids, segregation of the reactants can exist, which make the reaction rates and selectivities dependent on the mixing intensity. In chemical reactor engineering, the assumption is usually made that only mean concentrations need be considered. In reality, concentration values fluctuate about a mean, and in some cases these fluctuations must be considered in detail. This field is very complex and is still the subject of much research. This example serves only to introduce these concepts and to show how simulations can be made for certain simple situations. 

This cycle uses solid reactants. Small dendritic copper particles are used to carry out the last reaction to make the transformation of all the solid copper to CuCl, thereby maximizing hydrogen yield. The reported efficiency of this cycle is 49% [66]. This low temperature cycle is believed to eliminate many of the engineering and materials issues associated with the other two previously discussed cycles, however this cycle is also in the initial stages of development [111]. The temperature ranges are such that lower temperature nuclear reactors, e.g. sodium-cooled fast reactors, could be used with this cycle [69]. A hybrid version of this cycle is under investigation in Argonne National Laboratory [66,112]. 

R. E. Dahl, Jr., J. W. Bennett, eds., GFR Specialists Meeting on Absorbing Materials and Controls Rods for Fast Reactors, Dimitrovgrad, USSR, June 1973 Report HEDL-TME-73-91, Hanford Engineering Development Laboratory, Richland, WA, 1973. 

I HE Reactor Engineering Division of the Argonne National Laboratory is currently working on the design of a sodium-cooled fast reactor. Figure 1 shows the complexity of equipment that must remain compatible with, and operate in sodium at temperatures ranging from 580° to 900 °F. 

E R Adam and C V G Gregory "A Brief History of the Operation of the Prototype Fast Reactor at Dovinreay" The Nuclear Engineer, 1994,35,112 - 117... 

Studies of lead-bismuth and lead-cooled fast reactors are being carried out in the Russian Federation (RF) organizations Institute of Physics and Power Engineering (IPPE) and EDO... 

Session 3 Fast reactor physics and engineering experiments and analyses... 

The experimental fast reactor JOYO at the Japan Nuclear Cycle Development Institute s Oarai Engineering Center attained initial criticality in April 1977 and was the first liquid metal cooled fast reactor in Japan. From 1983 to 2000, JOYO operated with the MK-II core as an irradiation test bed to develop the fuels and materials for future Japanese fast reactors. Thirty-five duty cycle operations and thirteen special tests with the MK-II core were completed by June 2000 without any fuel pin failures or serious plant trouble. The reactor is currently being upgraded to the MK-III core. This paper provides a review of the operational experiences obtained through the JOYO s operation. 

The successful operations of JOYO provide a wealth of experiences with core management, impurity control, reactor engineering tests, innovative instrumentation techniques, operation and maintenance support systems, and component modifications. These experiences and accumulated data are to be used for the design of future fast reactors. They are also useful for upgrading the JOYO core and plant to the MK-III configuration and are essential to secure steady and safe reactor operation and enhance the irradiation capability of JOYO in the future. 

SAWADA, M., et al.. Experiment and Analysis on Natural Convection Characteristics in the Experimental Fast Reactor JOYO, Nuclear Engineering and Design, 120 (1990) pp. 341-347. 

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