| 摘要 |
NEUTRON DETECTION DEVICE FOR MEASURING THE POWER OF A NUCLEAR REACTOR The present invention relates to a neutron detection device for measuring the power of a nuclear reactor. This device (10) comprises a containment (11) inside which there is mounted a detector (12) and which contains a neutral gas. The detector is formed by a fission type chamber comprising a cylindrical-shaped external electrode (13), coated with a lining of uranium in metal form, enriched as isotope 235, and a cylindrical-shaped internal electrode (15) coaxial to the external electrode. The containment is of annular shape and arranges a cylindrical center space (18) open at both ends to house a moderator (19) to slow down the fast neutrons with great efficiency with respect to detection. This achievement has the advantage of making it easy to replace the moderator. It is favorable to use cylindrical electrodes of large diameter thus increasing the sensitivity. (Figure 1)
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