JPS6488288A - Analyzing apparatus of activated reinforced concrete - Google Patents

Analyzing apparatus of activated reinforced concrete

Info

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
Application number
JP24634087A
Other languages
Japanese (ja)
Inventor
Toru Fujita
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP24634087A priority Critical patent/JPS6488288A/en
Publication of JPS6488288A publication Critical patent/JPS6488288A/en
Pending legal-status Critical Current

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.
JP24634087A 1987-09-30 1987-09-30 Analyzing apparatus of activated reinforced concrete Pending JPS6488288A (en)

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)

* Cited by examiner, † Cited by third party
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

Cited By (5)

* Cited by examiner, † Cited by third party
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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