Sodium-cooled fast reactors | Zendy

A.I. Leipunskii | Zendy; O. D. Kazachkovskií | Zendy; I. I. Afrikantov | Zendy; M. S. Pinkhasik | Zendy; N.V. Krasnoyarov | Zendy; M. S. Poido | Zendy

AI Assistant Blog Pricing

Home ZAIA Blog

Open Access

Sodium-cooled fast reactors

Author(s) -

A.I. Leipunskii,

O. D. Kazachkovskií,

I. I. Afrikantov,

M. S. Pinkhasik,

N.V. Krasnoyarov,

M. S. Poido

Publication year - 1964

Publication title -

soviet atomic energy

Language(s) - English

Resource type - Journals

ISSN - 0038-531X

DOI - 10.1007/bf01116321

Subject(s) - nuclear engineering , burnup , scram , materials science , coolant , plutonium , blanket , decay heat , heat exchanger , mechanical engineering , engineering , chemistry , radiochemistry , composite material

Based on the operational experience of the experimental fast reactor BR-5, the prototype of a full-scale fast-reactor power station of 350 Mwe and 1000 Mwt is being designed. Fuel elements are stainless steel tubes filled with uranium and plutonium dioxides, ribbed for spacing, and inserted into subassemblies. The radial blanket consists of cylindrical elements filled with depleted UO{sub 2} and inserted into subassemblies. The reactor is controlled by B{sub 4}C elements. Burnup reactivity change is compensated by movable subassemblies. Reactivity changes due to heat and power rise are compensated by B{sub 4}C subassemblies. Similar B{sub 4}C subassemblies are used for reactor scram. The shieldling, fuel charge and discharge mechanism, pumps, heat exchangers, and steam generators are described, and the coolant parameters of the primary, secondary, and third loops are given. (M.J.T.)

The content you want is available to Zendy users.

Already have an account? Click here to sign in.

Having issues? You can contact us here

Accelerating Research