Study of construction materials for a lead-cooled reactor

作者：Bozin S N^*; Rodchenkov B S; Kashtanov A D; Markov V G; Yakovlev V A; Schenkova I A; Ivanov Yu A; Ioltukhovskiy A G; Leont'eva Smirnova M V

来源：Atomic Energy, 2013, 113(5): 320-326.

DOI：10.1007/s10512-013-9639-5

In the development process for the BREST-OD-300 lead-cooled fast reactor, 10Kh15N9S3B1 and 10Kh9NSMFB steels were chosen for the main equipment, the corrosion resistance and mechanical properties were investigated, and the effect of the lead coolant on the short-time mechanical properties, long-time strength, creep, low-cycle fatigue and crack kinetics under low-cycle loading were studied. 16Kh12MVSFBR steel was chosen for fuel-element cladding. The physical-mechanical, corrosion in liquid-lead flow, radiation, technological and other properties were studied. Complex-alloyed (Cr, Mo, W, Si, Al, N) steel or bimetallic (trimetallic) materials were studied as promising cladding materials.

• 出版日期2013-3