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CN-121995422-A - Site dosage rate measuring device and method

CN121995422ACN 121995422 ACN121995422 ACN 121995422ACN-121995422-A

Abstract

The invention relates to the technical field of cores and discloses a device and a method for measuring site dosage rate. According to the site dosage rate measuring device provided by the invention, the physical barrier is constructed through the sleeve pre-buried in the outer wall of the structure and the closed blind end thereof, the high dosage site is isolated from the external overhaul site, during measurement, the probe of the monitor is only required to be inserted into the measuring channel opened by the shielding compensation structure from the outside, personnel carrying equipment is not required to enter or approach the high dosage site, and temporary perforation is not required during measurement, so that aerosol disturbance, equipment surface pollution diffusion (cross pollution) and direct external irradiation and internal irradiation risks suffered by operators possibly caused by personnel entering the site are avoided. Meanwhile, as the blind end stretches into the high-dose place, the detector of the blind end completely penetrates through the structural wall body, the radiation field of the place to be detected is directly detected, and the dose rate of the real place without additional attenuation of the wall body is measured, so that the data are more accurate.

Inventors

  • Zeng long
  • LIU DONGKUN
  • MA XIAOFEN
  • HU JUNCHI
  • KANG LEI
  • ZHANG WEIMING
  • LI YONGJUN
  • CAO HONGMEI
  • LIU ZUQUAN
  • LIU XIAOGUANG
  • LIU YULEI
  • LI XIAOMENG
  • HAO YU

Assignees

  • 中国核电工程有限公司

Dates

Publication Date
20260508
Application Date
20260128

Claims (11)

  1. 1. A site dose rate measurement device, a structural exterior wall (B) of a high dose site (a) installed in a nuclear facility, characterized by comprising: The monitor is provided with a probe (101); the measurement interface subassembly, pre-buried in structure outer wall (B), the measurement interface subassembly includes: The sleeve (2) penetrates through the outer wall (B) of the structure, a closed blind end (201) is arranged at one end, which stretches into the high-dose place (A), of the sleeve (2), an open end (202) is arranged at one end, which is close to the overhaul place (C), of the sleeve (2), and a measuring channel is arranged between the open end (202) and the blind end (201) along the axial direction of the sleeve (2); A shielding compensation structure (3), wherein the shielding compensation structure (3) is arranged on the structure outer wall (B) and covers the opening end (202) of the sleeve (2), the shielding compensation structure (3) is used for opening or closing a measuring channel, and the shielding compensation structure (3) is used for compensating the shielding effect lost by the sleeve (2) penetrating the structure outer wall (B) when closing the measuring channel, so that the radiation shielding integrity of the structure outer wall (B) is maintained; When the measuring channel is opened, the probe (101) of the monitor can be inserted into the sleeve (2) through the channel and moved to the blind end (201) to measure the dosage rate of the high dosage place (A).
  2. 2. The site dosage rate measurement device of claim 1, wherein the shielding compensation structure (3) comprises an inner shielding block (301) and an outer shielding block which are detachably connected, the inner shielding block (301) is mounted on a structural outer wall (B), and the outer shielding block is mounted on one side of the inner shielding block (301) close to a maintenance site (C).
  3. 3. The field dose rate measuring device of claim 2, wherein the shielding compensation structure (3) further comprises a fastening mechanism for press-fixing the outer shielding block to the inner shielding block (301).
  4. 4. A venue dose rate measurement device according to claim 3, wherein the fastening mechanism comprises a handle (8) and a hold down structure (9), the hold down structure (9) opening or closing the outer shielding block in linkage with the handle (8).
  5. 5. The venue dose rate measurement device according to any of claims 2 to 4, wherein one end of the outer shielding block is hinged to one end of the inner shielding block (301).
  6. 6. The field dose rate measurement device of any one of claims 2-4, characterized in that a seal (4) is provided between the inner shielding block (301) and the open end (202) of the sleeve (2).
  7. 7. The venue dose rate measurement device according to any of claims 2 to 4, wherein the inner shielding block (301) is fixed to the structural outer wall (B) by means of anchors (5).
  8. 8. The site dosage rate measurement device of any one of claims 1-4, wherein the blind end (201) is adapted for sealing connection with a steel application surface within a high dosage site (a).
  9. 9. A method of site dose rate measurement, characterized in that a site dose rate measurement device as defined in any one of claims 1-8 is used, comprising an operation process comprising the steps of: When measurement is needed, operating at one side of a maintenance site (C), opening a shielding compensation structure (3) of a measurement interface assembly, and exposing a measurement channel of the sleeve (2); Inserting the probe (101) of the monitor into the sleeve (2) through the measurement channel until its measurement end reaches or approaches the blind end (201) of the sleeve (2); measuring the site dosage rate in the high dosage site (A) by a monitor and acquiring measurement data; After the measurement is completed, the probe (101) is taken out, the shielding compensation structure (3) is closed, and the measurement channel is closed again.
  10. 10. The site dosage rate measurement method of claim 9, further comprising, prior to the operation, a design process comprising the steps of: And designing the sleeve (2) with the blind end (201) according to the conditions of the outer wall (B) of the structure, the use requirements of workers and the requirements of standard specifications.
  11. 11. The site dosage rate measurement method of claim 10, further comprising, after the design process is completed and before the operation process is started, an installation process comprising the steps of: reserving mounting holes on the outer wall (B) of the structure; The sleeve (2) is penetrated into the mounting hole, so that one side of the blind end (201) of the sleeve (2) extends into the high-dosage place (A) and is in sealing connection with the steel coating surface of the high-dosage place (A); Filling a gap between the sleeve (2) and the mounting hole with a casting material; And installing a shielding compensation structure (3) at an opening end (202) of the sleeve (2) at one side of the overhaul field (C).

Description

Site dosage rate measuring device and method Technical Field The invention relates to the technical field of cores, in particular to a device and a method for measuring site dosage rate. Background During operation of the nuclear facility, the structural exterior wall of the high-radioactivity dosage site (such as between process equipment or waste liquid storage tanks) is a second closed barrier for guaranteeing radiation safety, and the interior of the structural exterior wall is generally provided with process pipelines, equipment and storage tanks with radioactivity. The equipment and the pipe fittings in the place need to be regularly overhauled or replaced due to corrosion, abrasion and strong irradiation aging which can occur in the long-term operation of the system. However, the level of radiation inside such sites is often extremely high, and personnel cannot access at will, and personnel must be arranged to enter into service after pre-evaluation and ensuring that the radiation exposure after access can be controlled to safe levels. At present, a radiation evaluation method is generally adopted before a high-dose place is entered, wherein the place is firstly cleaned and decontaminated initially, and then an operator uses a portable long-rod gamma dose rate measuring instrument and a portable aerosol sampler to extend into the room through a preset washing hole to respectively measure the gamma dose rate and the aerosol radioactivity concentration of the place. And carrying out safety evaluation according to the measurement result, and approving personnel to enter after confirming that the radiation protection requirement of personnel entering is met. However, based on radiation protection principles of validity of radiation practice, radiation protection optimization and personal dose equivalent limit, during measurement of site dose rate of high dose site through wash hole using portable long-rod gamma gauge, although the high dose site is continuously ventilated to maintain negative pressure environment, deterministic effect and random effect may occur to produce pollution dispersion to cause cross contamination, and cause risk of internal irradiation and external irradiation to staff in measurement operation, it is difficult to fully satisfy radiation protection requirement. Disclosure of Invention The invention provides a device and a method for measuring the site dosage rate, which are used for solving the problem that the radiation protection requirement cannot be met due to the fact that cross contamination is easy to cause in the traditional site dosage rate detection process. In a first aspect, the present invention provides a site dosage rate measurement device for installation on an exterior wall of a structure in a high dosage site of a nuclear facility, comprising a monitor and a measurement interface assembly. The measuring interface assembly is embedded in the structure outer wall and comprises a sleeve and a shielding compensation structure, wherein the sleeve penetrates through the structure outer wall, a closed blind end is arranged at one end of the sleeve, which stretches into the high-dose place, an open end is arranged at one end of the sleeve, which is close to the overhaul place, a measuring channel is arranged between the open end and the blind end along the axis direction of the sleeve, the shielding compensation structure is arranged on the structure outer wall and covers the open end of the sleeve, the shielding compensation structure is used for opening or closing the measuring channel, the shielding compensation structure is used for compensating the shielding effect lost due to the fact that the sleeve penetrates through the structure outer wall when the measuring channel is closed, radiation shielding integrity of the structure outer wall is maintained, and when the measuring channel is opened, the probe of the measuring instrument can be inserted into the sleeve through the channel and moved to the blind end to measure the dose rate of the high-dose place. The device has the beneficial effects that a physical barrier is constructed through the sleeve pre-buried in the outer wall of the structure and the closed blind end thereof, the high-dose place is separated from the external overhaul place, and during measurement, a probe of the monitor is only required to be inserted from the outside through a measuring channel opened by the shielding compensation structure, personnel carrying equipment is not required to enter or approach the high-dose place, and temporary perforation is not required during measurement, so that aerosol disturbance, equipment surface pollution diffusion (cross pollution) and direct external irradiation and internal irradiation risks suffered by operators possibly caused by personnel entering the place are avoided. Meanwhile, as the blind end stretches into the high-dose place, the detector of the blind end completely penetrates through the st