scholarly journals Potential of duplex fuel in prebreeder, breeder, and power reactor designs: tests and analyses (AWBA Development Program)

1982 ◽  
Author(s):  
T.L. Chao ◽  
J.J. Brennan ◽  
E. Duncombe ◽  
M.J. Schneider ◽  
R.G.R. Johnson
MRS Bulletin ◽  
1989 ◽  
Vol 14 (7) ◽  
pp. 48-52 ◽  
Author(s):  
Dale L. Smith

The next major step in the development of fusion power involves the design, construction, and operation of an experimental power reactor. The general objective of this type of device is to demonstrate key plasma physics, materials, and engineering performance under conditions that approach those considered necessary to establish the technical feasibility of fusion power. This device is generally perceived to be a tokamak configuration that operates on the deuterium-tritium (D-T) fuel cycle, which would produce several hundred megawatts of fusion power. Although a number of conceptual design studies on this type of device have been conducted, the current effort is focused on the International Thermonuclear Experimental Reactor (ITER) activity, a joint undertaking of the European Community (EC), Japan, the United States, and the Soviet Union, conducted under the auspices of the International Atomic Energy Agency (IAEA).The development of fusion power as an energy source depends to a large extent on the proper selection of materials for the various components. these materials will be exposed to a wide variety of conditions such as plasma particle and neutron radiation, high thermal fluxes, large thermal and mechanical stress, various chemical environments, and high magnetic fields. In order to achieve the high performance desired for a commercial power reactor, considerable materials development will be required. Because of the relatively near term time scale projected for ITER and the limited objectives, more conventional materials with more extensive data bases will be used where possible. Even so, a substantial materials development program is required to support a test reactor like ITER.


Author(s):  
Insik Kim ◽  
Sung-Goo Chi ◽  
Keun-Bae Yoo

Korean nuclear industry has demonstrated a success of KSNP (Korean Standard Nuclear Power Plant) program through operations of its six units starting from Ulchin 3&4 since 1998, and four more units are currently under construction with its new name of OPR1000 (Optimized Pressurized Reactor 1000). During the past 20 years of OPR1000 constructions and operations, Korean nuclear industry has put continuous effort to secure its better confidence in safety and performance. As a result, OPR1000 is showing the highest capacity factor and the lowest unplanned trip records among the worldwide operating nuclear power plants. The goal of APR1000 (Advanced Power Reactor 1000) program launched recently is to develop an improved version of OPR1000 design. It is required to adopt selected advanced design features of APR1400 (Advanced Power Reactor 1400) and to fulfill the new and strengthened design requirements including longer plant lifetime, colder head reactor, longer refueling interval, enhanced cyber security, etc. It is also essential to consider regional specific conditions such as electric frequency, sea water temperature and seismic conditions, etc. In this paper, the overall APR1000 development program is introduced, and design requirements as well as advanced design features (ADFs) for APR1000 are discussed comparing with those for OPR1000.


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