Analysis of Experimental Data on Gas Release and Swelling of Uranium Mononitride Fuel Irradiated in the BR-10 Reactor


如何引用文章

全文:

开放存取 开放存取
受限制的访问 ##reader.subscriptionAccessGranted##
受限制的访问 订阅存取

详细

The results of an investigation of gas release and swelling of uranium mononitride fuel after irradiation in standard and experimental fuel assemblies in the BR-10 reactor in the burnup range 3.4–8.4% h.a. are presented and analyzed. The results obtained were used to verify the fuel code DRAKON.

作者简介

S. Porollo

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

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Obninsk

S. Ivanov

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

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Obninsk

E. Marinenko

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

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Obninsk

L. Zabud’ko

Innovation-Technology Center for Project Breakthrough (ITTsP Proryv)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

补充文件

附件文件
动作
1. JATS XML

版权所有 © Springer Science+Business Media New York, 2017