Comparison of pressurized water reactor core characteristics for 100% plutonium-containing loadings

被引:24
作者
Kasemeyer, U [1 ]
Paratte, JM
Grimm, P
Chawla, R
机构
[1] Paul Scherrer Inst, CH-5232 Villigen, Switzerland
[2] Swiss Fed Inst Technol, CH-1015 Lausanne, Switzerland
关键词
Pu-burning PWR cores; U-free LWR fuel; three-dimensional care analysis;
D O I
10.13182/NT98-A2850
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The large quantities of reactor-grade (RG) and weapons-grade (WG) Pu accumulated worldwide could be reduced by employing 100% mixed-oxide (MOX) cores in light water reactors. The buildup of new Pu from the U present in the MOX, however, remains disadvantageous from the viewpoint of inventory reduction and also enhances the need for multiple recycling. A more effective way would be to use U-free fuel so that no new Pu is produced. A comparison is made, from rite physics design viewpoint, between the potential and the possible difficulties for two different types of Pu-burning pressurized water reactor cares, namely, 100% MOX and 100% uranium-free Pu fuel. The latter employs ZrO2 as inert matrix and Er2O3 as burnable poison, In each case, RG and WG Pu have been considered separately. The characteristics of the four different cores have been studied on the basic of three-dimensional calculations for an equilibrium cycle, a real-life UO2-fueled core being considered as reference for comparison purposes. For all four Pu-burning cases, it appears possible to design a four-region core with a natural cycle length of more than 300 days. For the 100% MOX cores, the Pu mass is reduced during irradiation by similar to 35% of the initial Pu inventory. For the U-free cores, the consumption is about twice as much, i.e., similar to 60% for the RG-Pu fuel and over 70% for the WG-Pu core. The reactivity balance in going from hot full power to hot Zero power conditions shows that while the 100% MOX core with RG Pu would need more effective control rods, both types of U-free cares have larger shutdown margins than the reference case. Consideration of the reactivity coefficients indicates that a steam-line-break accident could be mom problematic in the MOX core with RG Pu than in the other Eases. The rod ejection transient should be safe because the maximum inserted worth of a control rod is similar to 0.5 $. More detailed investigations of transient behavior-particularly for the U-free cores-are needed, the current study having considered feasibility mainly from the viewpoint of static physics considerations.
引用
收藏
页码:52 / 63
页数:12
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