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Advanced Reactors: Physics, Design and Economics. by J. M. Kallfelz, R. A. Karam

By J. M. Kallfelz, R. A. Karam

Complex Reactors: Physics, layout and Economics comprises the court cases of the foreign convention held at Atlanta, Georgia on September 8-11, 1974.
Organized in response to the classes of the convention, this e-book first describes the nationwide courses for the improvement of complicated reactors. next classes facilities on economics of complex reactors; advancements in reactor thought; complex reactor experiments and research; move part information and calculational equipment. The final 3 classes specialise in sensitivity research of necessary reactor parameters; difficulties within the layout of complex reactors; and the layout and operational event for complicated reactors.

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Additional info for Advanced Reactors: Physics, Design and Economics. Proceedings of the International Conference Held at Atlanta, Georgia, September 8–11, 1974

Example text

Some ways of increas­ ing this important factor have been already mentioned above. When passing to reactors of a higher power there arise some additional possibilities of Increasing the breeding ratio through increasing the internal breeding coefficient. A possi­ bility of a mixed (lr - Pu ) fuel charge into the reactor has been considered that results in additional flattening and sta­ bilization of heat realease and can be used to accelerate the introduction of fast reactor capacities in the first stage at limited plutonium resources (8).

1 : DEBENELUX Common Fast Breeder Project As we see, the common project is organized on several l e v e l s ; the Govern­ ment level, the level of the Research Centers, the level of the industries and also of utilities. I shall not go into the details of how the common project really is operated. There is a Common Project Committee where from the four coun­ tries Governments , Centers, Industry and Utilities are at the same table. It coordinates the whole project with the goal to build the sodium cooled SNR 300.

Thermal power 2. Specific capacity 3, Neutron flux 4. Sodium temperature at 5- fuel assembly outlet Sodium temperature at reactor outlet i i t Units MW kw/l of the core n/cm sec• Y" f t 1 Values 52 1100 3,7*10 15 *C 630 °C 520 design was started. The systems subjected to reconstruction as a result of the revealed defects included the following ones: - oil systems for circulating pumps; - the heat-removal system under transient conditions of a reactor emergency shut-down; ~ the refuelling system; - the reactor control and safety equipment* As a whole, the B0R-60 plant operation has provided an additional proof of a possibility of large fast reactors creat­ ing and reliable operating.

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