A gas scintillation monitor for tritium gas in argon or in nitrogen

被引:2
作者
Campi, F [1 ]
Mascherpa, C [1 ]
Sterlini, C [1 ]
Pacenti, P [1 ]
Terrani, S [1 ]
机构
[1] JRC EURATOM, INST SAFETY TECHNOL, I-21020 ISPRA, VA, ITALY
来源
HEALTH PHYSICS | 1996年 / 71卷 / 03期
关键词
tritium; scintillation chamber; nuclear fuel cycle; nitrogen;
D O I
10.1097/00004032-199609000-00010
中图分类号
X [环境科学、安全科学];
学科分类号
08 ; 0830 ;
摘要
For civilian purposes tritium is presently used in quantities of tens of PBq (MCi) in laboratories for the studies of tritium technology, at the Joint European Torus plant (Abingdon, Oxon, OX143A, UK) as fuel for the process of nuclear fusion, and in the manufacture of radio-luminescent items. Given the extreme mobility of tritium in most materials, it is necessary to use systems for double containment, such as glove boxes or spaces between primary and secondary containers, in which inert gas like argon or nitrogen flows. With these systems it is possible to recover tritium that escapes from the primary containment. Presently the gas flow is monitored continuously by means of ionization chambers which may present problems in particular applications (''memory effect'' with high activity, strong dependence of the response on the presence of impurity, etc.). The aim of the work here presented is to determine the prospects for the realization of a new type of monitor mainly dedicated to the measurement of gas activity in isolation space of the containing systems of the high activity tritium plants. This monitor should have sufficient sensitivity, quick response, and should be easily decontaminated. As a detection technique we chose the scintillation produced in the inert gas by radioactive decay. With the first prototype, designed in cylindrical form, it was possible to observe gaseous scintillation events in mixture of tritium and argon or nitrogen. Following that, a spherical prototype was designed, of which we studied the performances and the dependence of the response varying the pressure, the concentration of tritium, the percentage of the impurity, and the gas flow rate. The results are satisfactory and suggest that the monitor could be used in glove boxes and double containment systems. The future research program will include tests involving large quantities of tritium and a study of the ideal dimensions and geometry of the detection chamber in order to optimize the detector response.
引用
收藏
页码:335 / 339
页数:5
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