Tests of Models of BREST-OD-300 Reactor Fuel Elements in an Autonomous Lead-Cooled Channel of a BOR-60 Reactor

By Kordyukov A. G.  

Atomic Energy, Vol. 97, Iss. 2, 2004-08 ,pp. : 564-570

Springer Publishing Company

Access to resources Recommend Favorite

Analysis of a Benchmark Experiment on the Hydraulics and Heat Transfer in a Liquid-Metal-Cooled Assembly of Fuel-Element Simulators

By Zhukov A.   Kuzina Yu.   Sorokin A.  

Atomic Energy, Vol. 99, Iss. 5, 2005-11 ,pp. : 770-781

Springer Publishing Company

Access to resources Recommend Favorite

Particulars of the In-Reactor Behavior of VVER and PWR Uranium Dioxide Fuel with Pellets of Different Geometry

By Volkov B.   Yakovlev V.   Ryazantsev E.   Kalygin V.   Burukin A.   Ivanov A.   Pimenov Yu.  

Atomic Energy, Vol. 114, Iss. 3, 2013-07 ,pp. : 169-176

Springer Publishing Company

Access to resources Recommend Favorite

Recommendations for calculating the characteristics of thermal creep of mixed uranium–plutonium oxide fuel when analyzing fuel-element serviceability

By Malygin V.  

Atomic Energy, Vol. 108, Iss. 1, 2010-05 ,pp. : 15-20

Springer Publishing Company

Access to resources Recommend Favorite

Fuel cycle of a brest fast reactor in an americium transmutation regime

By Kvaratskheli A.   Knyazev A.   Konev V.   Kochurov B.  

Atomic Energy, Vol. 97, Iss. 3, 2004-09 ,pp. : 593-597

Springer Publishing Company

Access to resources Recommend Favorite