Low pressure distillation is a promising technology for the recovery and purification of carrier salts (LiF-BeF
2
) in the thorium based molten salt reactors (TMSR).
Purpose:
This study aims to compare the separation behavior of NdF
3
before and after adding the oxidant CaO in FLiNaK molten salt.
Methods:
Precipitation-distillation coupled method was employed in purification of molten salt. Then the X-ray Diffractio
n
(XRD) was applied to the analysis of the produced NdF
3
in the molten salt.
Results:
At high temperature
CaO was confirmed to react with NdF
3
and form rare earth oxide Nd
2
O
3
insoluble in molten salt. At 730℃
the conversion rate for Nd was up to 95%. After the precipitation reaction
the separation rate under low pressure distillation was compared with the preceding one. The decontamination factor of Nd was deduced to 9.4×10
5
whilst the value was 3.1×10
4
without adding CaO. Meanwhile
the evaporation rate also was improved after precipitation.
Conclusion:
The combination of the precipitation and distillation treatment is an effective way to achieve the high throughput performance in the salt separation process.
关键词
Keywords
references
J Uhlir . Chemistry and technology of Molten Salt Reactors-history and perspectives . Journal of Nuclear Materials , 2007 . 360 ( 1 ): 6 - 11 . DOI: 10.1016/j.jnucmat.2006.08.008 http://doi.org/10.1016/j.jnucmat.2006.08.008 .
Rosenthal M W, Haubenreich P N, Briggs R B. The development status of molten-salt breeder reactors[R].USA:Oak Ridge National Laboratory, 1972.
Hightower J R, Mcneese L E. Measurement of the relative volatilities of fluorides of Ce, La, Pr, Nd, Sm, Eu, Ba, Sr, Y and Zr in mixtures of LiF and BeF 2 [R]. USA:Oak Ridge National Laboratory, 1968.
Carter W L, Lindauer R B, Mcneese L E. Design of an engineering-scale, vacuum distillation experiment for molten-salt reactor fuel[R]. USA:Oak Ridge National Laboratory, 1968.
Hightower J R, Mcneese L E. Low-pressure distillation of molten fluoride mixtures:nonradioactive tests for the MSRE distillation experiment[R]. USA:Oak Ridge National Laboratory, 1971.
Y Z Cho , H C Yang , G H Park , . Treatment of a waste salt delivered from an electrorefining process by an oxidative precipitation of the rare earth elements . Journal of Nuclear Materials , 2009 . 384 ( 3 ): 256 - 261 . DOI: 10.1016/j.jnucmat.2008.11.020 http://doi.org/10.1016/j.jnucmat.2008.11.020 .
J H Choi , I H Cho , H C Eun , . Fabrication and physical properties of lanthanide oxide glass wasteform for the immobilization of lanthanide oxide wastes generated from pyrochemical process . Journal of Radioanalytical and Nuclear Chemistry , 2014 . 299 ( 3 ): 1731 - 1738 . DOI: 10.1007/s10967-013-2863-6 http://doi.org/10.1007/s10967-013-2863-6 .