| 摘要 |
<p>1,111,959. Processing spent nuclear fuel. COMMISSARIAT A L'ENERGIE ATOMIQUE. 28 June, 1966 [29 June, 1965], No. 28992/66. Heading G6R. [Also in Division G3] In the separation of uranium and plutonium from fission products by countercurrent extraction of an aqueous solution with a solvent, for example tributyl phosphate, the process is regulated electronically by measuring the plutonium retention in intermediate extraction stages by means of a neutron detector in each stage, integrating the impulses received from the detectors to provide a voltage which drives a motor associated with the feeding means for one of the liquid phases, so as to vary the ratio of the solvent flow rate to the aqueous solution flow rate. The neutron detectors may comprise cylindrical copper cathodes and coaxial anodes and may be filled with BF 3 enriched with B10. An alarm is provided to warn of excessive plutonium leakage.</p> |
