Gen-IV Reactor Systems Criteria Implementation in BN-1200


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Аннотация

The design of the BN-1200 sodium-cooled fast reactor is analyzed from the standpoint of its compliance with the criteria fitting the promising Gen-IV reactor facilities. The basic technical solutions adopted in the BN-1200 design making it possible to meet the requirements of consistent development of non-proliferation and safety, cost-effectiveness, and physical protection are described. The BN-1200 concept is evaluated on the basis of 26 criteria developed as part of the Generation IV international forum for the Gen-IV sodium-cooled fast reactor. The compliance of the safety requirements used in the development of the BN-1200 design with the design criteria for the Gen-IV sodium-cooled fast reactor developed as part of the Generation IV international forum is analyzed.

Авторлар туралы

Yu. Ashurko

State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)

Email: j-atomicenergy@yandex.ru
Ресей, Obninsk

A. Gulevich

State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)

Email: j-atomicenergy@yandex.ru
Ресей, Obninsk

D. Klinov

State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE)

Email: j-atomicenergy@yandex.ru
Ресей, Obninsk

B. Vasil’ev

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Ресей, Nizhnii Novgorod

A. Vasyaev

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Ресей, Nizhnii Novgorod

E. Marova

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Ресей, Nizhnii Novgorod

S. Shepelev

Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov)

Email: j-atomicenergy@yandex.ru
Ресей, Nizhnii Novgorod

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