FIELD: monitoring and verification technologies.
SUBSTANCE: device for radiation and temperature monitoring of a decommissioned uranium-graphite reactor comprises a sealed housing with a flange and a sealed passage, in which direct-charge neutron detectors and cable-type thermoelectric converters are provided, as well as detector attachment elements. Housing consists of links and is made in the form of elongated collecting pipe, one end of which is plugged and on external part of which there is a thread for installation of collimator and / or protective shield. On the other side the flat flange is screwed, on which eye-bolts are installed. On top, a cover is installed on the flange through the gasket, in which holes are provided for passage of wires from the thermal converter and the gamma-radiation detecting unit, which are installed in the guides located in the lower part of the elongated mounting pipe and connected to it by means of a welded joint.
EFFECT: invention makes it possible to increase efficiency of using known devices owing to possibility of arrangement of the device in inspection channels of various geometry and curvature.
3 cl, 3 dwg
Title | Year | Author | Number |
---|---|---|---|
METHOD OF MONITORING INTEGRITY OF SAFETY BARRIERS DURING DECOMMISSIONING OF URANIUM-GRAPHITE NUCLEAR REACTOR | 2018 |
|
RU2694817C1 |
METHOD OF MONITORING STABILITY OF INTERNAL SAFETY BARRIERS AT STORAGE POINT OF URANIUM-GRAPHITE REACTOR | 2015 |
|
RU2579822C1 |
METHOD FOR DETERMINING PARAMETERS OF VOLUMETRIC DISTRIBUTION OF NUCLEAR FUEL IN STACK OF STOPPED URANIUM-GRAPHITE REACTOR | 2023 |
|
RU2811570C1 |
METHOD OF NUCLEAR FUEL FRAGMENTS DETECTING AND PARAMETERS DETERMINING IN THE STOPPED URANIUM GRAPHITE REACTOR STACK | 2017 |
|
RU2649656C1 |
SYSTEM FOR DETECTING NUCLEAR FUEL FRAGMENTS IN GRAPHITE UNITS OF NUCLEAR REACTOR AND DETERMINING THEIR PARAMETERS | 2023 |
|
RU2822538C1 |
METHOD FOR DETECTING NUCLEAR FUEL FRAGMENTS AND DETERMINING THEIR PARAMETERS IN NUCLEAR REACTOR GRAPHITE BLOCKS | 2022 |
|
RU2798506C1 |
SCANNER FOR CHECKING SPATIAL DISTRIBUTION OF POWER OF GAMMA-RAY EMISSION IN ACTIVE ZONE OF URANIUM-GRAPHITE REACTOR | 2003 |
|
RU2248010C2 |
PROCESS AND DEVICE OF SPENT NUCLEAR FUEL BURNUP DETECTION | 2006 |
|
RU2328043C2 |
DETECTOR ASSEMBLY FOR REACTOR INTERNAL MONITORING SYSTEM | 1999 |
|
RU2140105C1 |
METHOD OF DUMPING OF TECHNOLOGICAL MINE FOR RADIOACTIVE WASTES AT DECOMMISSIONING OF URANIUM GRAPHITE REACTOR | 2016 |
|
RU2625169C1 |
Authors
Dates
2020-03-05—Published
2019-11-29—Filed