CALCULATION MODEL FOR PREDICTING CONCENTRATIONS OF RADIOACTIVE CORROSION PRODUCTS IN PRIMARY COOLANT OF BOILING WATER-REACTORS

被引:23
作者
UCHIDA, S [1 ]
KIKUCHI, M [1 ]
ASAKURA, Y [1 ]
YUSA, H [1 ]
OHSUMI, K [1 ]
机构
[1] HITACHI LTD,HITACHI WORKS,HITACHI,JAPAN
关键词
D O I
10.13182/NSE78-A15439
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
A calculation model was developed to predict the shutdown dose rate around the recirculation pipes and their components in boiling water reactors (BWRs) by simulating the corrosion product transport in primary cooling water. The model is characterized by separating cobalt species in the water into soluble and insoluble materials and then calculating each concentration using the following considerations: Insoluble cobalt (designated as crud cobalt) is deposited directly on the fuel surface, while soluble coabalt (designated as ionic cobalt) is adsorbed on iron oxide deposits on the surface. Cobalt-60 activated on the fuel surface is dissolved in the water in an ionic form, and some is released with iron oxide as crud. The model can follow the reduction of **6**0Co in the primary cooling water caused by the control of the iron feed rate into the reactor, which decreases the iron oxide deposits on the fuel surface and then reduces the cobalt adsorption rate. The calculated results agree satisfactorily with the measurements in several BWR plants.
引用
收藏
页码:247 / 254
页数:8
相关论文
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