JPS6488288A - Analyzing apparatus of activated reinforced concrete - Google Patents
Analyzing apparatus of activated reinforced concreteInfo
- Publication number
- JPS6488288A JPS6488288A JP24634087A JP24634087A JPS6488288A JP S6488288 A JPS6488288 A JP S6488288A JP 24634087 A JP24634087 A JP 24634087A JP 24634087 A JP24634087 A JP 24634087A JP S6488288 A JPS6488288 A JP S6488288A
- Authority
- JP
- Japan
- Prior art keywords
- neutron flux
- container
- shielding wall
- thermal neutron
- data
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Abstract
PURPOSE:To determine rapidly and definitely the extent of reinforced concrete to be separated and dismantled as radioactive waste, by a method wherein the activated radioactivity distribution of a each nuclide in a biological shielding wall is determined indirectly from the product amount of <60>CO produced in a primary container. CONSTITUTION:A gamma-ray measuring device 15 measures a radiation emitted from <60>CO in a primary container 13. A counting rate-neutron flux conversion factor relating to the container 13, thermal neutron flux distribution data determined by a computation analysis for every representative position, data on concrete and rods in a biological shielding wall 3, etc. are stored in a data storage device 17. An analytical computation device 19 determines the product amount of <60>CO at each measuring position in the container 13 from a measured value of the measuring device 15, computes a thermal neutron flux distribution on the surface of the container 13 and determines the thermal neutron flux distribution in the direction of the depth in the shielding wall 3 at each measuring position from the data stored in the storage device 17. An activated radioactivity distribution of each nuclide in the shielding wall 3 is calculated at every measuring position from the thermal neutron flux distribution thus determined and the data stored in the storage device 17, and determines a cut depth of reinforced concrete to be cut out as radioactive waste.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP24634087A JPS6488288A (en) | 1987-09-30 | 1987-09-30 | Analyzing apparatus of activated reinforced concrete |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP24634087A JPS6488288A (en) | 1987-09-30 | 1987-09-30 | Analyzing apparatus of activated reinforced concrete |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6488288A true JPS6488288A (en) | 1989-04-03 |
Family
ID=17147109
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP24634087A Pending JPS6488288A (en) | 1987-09-30 | 1987-09-30 | Analyzing apparatus of activated reinforced concrete |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6488288A (en) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2001004747A (en) * | 1999-06-25 | 2001-01-12 | Takenaka Komuten Co Ltd | Method and device for monitoring radiation-shielding performance of concrete structure for shielding radiation after hardening |
CN103454669A (en) * | 2012-05-28 | 2013-12-18 | 中国原子能科学研究院 | Method for graduating barreled nuclear waste neutron measuring device |
US8853638B2 (en) | 2012-02-17 | 2014-10-07 | The Japan Atomic Power Company | Radioactivity evaluation method and radioactivity evaluation system |
JP2018141669A (en) * | 2017-02-27 | 2018-09-13 | 清水建設株式会社 | Method for estimating non-radioactivated portion in concrete |
JP2019211256A (en) * | 2018-05-31 | 2019-12-12 | 三菱重工業株式会社 | Radioactivity concentration display device, radioactivity concentration calculation device, radioactivity concentration display method and radioactivity concentration calculation method |
-
1987
- 1987-09-30 JP JP24634087A patent/JPS6488288A/en active Pending
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2001004747A (en) * | 1999-06-25 | 2001-01-12 | Takenaka Komuten Co Ltd | Method and device for monitoring radiation-shielding performance of concrete structure for shielding radiation after hardening |
US8853638B2 (en) | 2012-02-17 | 2014-10-07 | The Japan Atomic Power Company | Radioactivity evaluation method and radioactivity evaluation system |
CN103454669A (en) * | 2012-05-28 | 2013-12-18 | 中国原子能科学研究院 | Method for graduating barreled nuclear waste neutron measuring device |
JP2018141669A (en) * | 2017-02-27 | 2018-09-13 | 清水建設株式会社 | Method for estimating non-radioactivated portion in concrete |
JP2019211256A (en) * | 2018-05-31 | 2019-12-12 | 三菱重工業株式会社 | Radioactivity concentration display device, radioactivity concentration calculation device, radioactivity concentration display method and radioactivity concentration calculation method |
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