Neutronenfluss-Messvorrichtung fuer fluessigkeitsgekuehlte Kernreaktoren

摘要

1320476 Controlling reactors; fuel elements COMMISSARIAT A L'ENERGIE ATOMIQUE 7 Jan 1972 [20 Jan 1971] 825/72 Heading G6C A nuclear reactor, which may be a fast sodium-cooled power reactor, includes a neutron flux measurement installation in which a neutron detection chamber 34 is placed beneath the reactor vessel 10 and a tubular enclosure 36 containing an inert gas, such as argon or helium, is disposed in the core and has a depending portion 38 which extends adjacent the chamber 34. The enclosure 36 is similar in profile-shape to a fuel element assembly 20 which is supported by a diagrid 26 from which liquid sodium can be passed to the assembly interior. The assembly has an upper neutron-absorbent structure 31 shaped as at 33 for handling by a geals-device. The enclosure 36 is similarly shaped and includes a neutron-absorbent block 40. The portion 38 extends through a mass 12 of liquid sodium so that its lower end is adjacent chamber 34 which is outside a safety shield comprising stainless steel 14 lined with insulating material 16. The enclosure 36 and chamber 34 can be on the axis of the reactor core, or vertically below the boundary between the core and a radial blanket of fertile material. More than one such installation may be provided.