CHEMICAL FORM OF THE SOLID FISSION-PRODUCTS IN (TH,U) O2 SIMULATING HIGH BURNUP

被引:18
作者
UGAJIN, M
SHIRATORI, T
SHIBA, K
机构
[1] Thorium Fuel Laboratory, Japan Atomic Energy Research Institute, Ibaraki-ken, Tokai-mura
关键词
D O I
10.1016/0022-3115(79)90148-X
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The chemical form of the solid fission products has been studied for (Th0.81U0.19) O2 simulating 21.5% FIMA in an HTGR environment. Experiments have been performed with X-ray diffraction, electron-probe microanalysis, ceramography and hardness measurement. The results showed that fission-product phases of two types, Mo-Ru-Pd and (Ba, Sr)(Zr, Ce) O3, are present in the simulated fuel pellet. The fuel matrix comprises (Th1-xUx, Zr, Ce, RE) O2 with an x value of 0.067(RE = Nd, La, Pr, Y, Sm). Dissolution of the rare earths (RE) and the residual Zr plus Ce in (Th0.933U0.067) O2 was accompanied by contraction of the unit cell of the oxide matrix. Reaction behavior in the selected fission product system BaO-ZrO2-Nd2O3 was also investigated. The results showed that in the presence of BaO, Nd2Zr2O7 is converted to barium zirconate: at 1630°C, Nd2Zr2O7 + 2 BaO → 2 BaZrO3 + Nd2O3. This fact, combined with thermochemical assessment, confirms the relative stability of (Ba, Sr)(Zr, Ce) O3 against Nd2Zr2O7 in the simulated (Th0.81U0.19) O2. From these results and fission product inventories, it is inferred that the chemical state of high-burnup ThO2 is very similar to that of (Th0.81U0.19) O2. © 1979.
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页码:26 / 38
页数:13
相关论文
共 45 条
[1]  
BARIN I, 1977, THERMOCHEMICAL PRO S
[2]  
Barin I., 1973, THERMOCHEMICAL PROPE
[3]  
Bell M.J, 1973, ORNL4628
[4]  
Berman R M, 1976, WAPDTM1236
[5]   ELECTRON PROBE MICRO-ANALYSIS OF IRRADIATED UO2 [J].
BRADBURY, BT ;
DEMANT, JT ;
MARTIN, PM ;
POOLE, DM .
JOURNAL OF NUCLEAR MATERIALS, 1965, 17 (03) :227-&
[6]  
BRADBURY BT, 1966, R5149 UKAEA AERE REP
[7]   METALLIC FISSION-PRODUCT INCLUSIONS IN IRRADIATED OXIDE FUELS [J].
BRAMMAN, JI ;
SHARPE, RM ;
THOM, D ;
YATES, G .
JOURNAL OF NUCLEAR MATERIALS, 1968, 25 (02) :201-&
[8]   METAL FISSION-PRODUCT BEHAVIOR IN HIGH-TEMPERATURE REACTORS-UO2 COATED PARTICLE FUEL [J].
BROWN, PE ;
FAIRCLOTH, RL .
JOURNAL OF NUCLEAR MATERIALS, 1976, 59 (01) :29-41
[9]   FISSION PRODUCT EFFECTS IN URANIUM DIOXIDE [J].
CHILDS, BG .
JOURNAL OF NUCLEAR MATERIALS, 1963, 9 (03) :217-244
[10]   A METALLOGRAPHIC AND X-RAY STUDY OF LIMITS OF OXYGEN SOLUBILITY IN UO2-THO2 SYSTEM [J].
COHEN, I ;
BERMAN, RM .
JOURNAL OF NUCLEAR MATERIALS, 1966, 18 (02) :77-&