Z. Suud et H. Sekimoto, DESIGN AND SAFETY ASPECT OF LEAD AND LEAD-BISMUTH COOLED LONG-LIFE SMALL SAFE FAST-REACTORS FOR VARIOUS CORE CONFIGURATIONS, Journal of Nuclear Science and Technology, 32(9), 1995, pp. 834-845
Design and safety aspects of long-life small safe fast reactors using
liquid lead or lead-bismuth coolant with metallic or nitride fuel are
discussed. Neutronic analyses are performed to investigate the effect
of core height to diameter ratio (H/D) on design performance of the pr
oposed reactors. All reactors are subjected to the constraint of 12 ye
ars operation without refueling and shuffling with constant 150 MWt re
actor power and also to the requirement of maximum excess reactivity d
uring burnup to be less than 0.1%Delta k. The results show that the pa
ncake design with H/D of similar to 2/3 gives the most negative coolan
t void coefficient under the requirements for excess reactivity. Modif
ied designs with the central region axially fulfilled with fertile mat
erial are proposed to improve the coolant void coefficient. Thermal-hy
draulic analysis results show the possibility to operate the reactors
up to the end of life without changing their orifice pattern, necessar
y pumping power for the proposed design smaller than the conventional
large sodium cooled FBR, and the natural circulation contribution of 2
5-40% at the normal operating condition. The reactivity feedback coeff
icients are also estimated and appeared to be negative for all the com
ponents including the coolant density coefficient.