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公开(公告)号：JPH05107384A
公开(公告)日：1993-04-27
申请号：JP26488791
申请日：1991-10-14
Applicant: TOSHIBA CORP
Inventor： YOSHIMURA YUKIO , GOTO TETSUO , FUKAZAWA TAKUJI
Abstract: PURPOSE:To efficiently and accurately measure and evaluate the radiation intensity of a subject to be measured by using a simple method corresponding to the subject to be measured in measuring the density of the subject to be measured which cannot be regarded as being uniform. CONSTITUTION:A radiation measuring apparatus is provided with a measurement container 2, a radiation distribution measuring instrument 3, a radiation polluted position measuring instrument 4 and a data processing unit 5. A calibration curve R for correcting density is originated in advance using a sample M made of the same material as a subject 12 to be measured and having uniform density, and the position and the radiation intensity of the radiation source P1 of the subject 12 to be measured being nonuniform in density are measured by the radiation distribution measuring instrument 3 and the radiation polluted position measuring instrument 4, and, from data about density measured by the radiation distribution measuring instrument 3 and data about polluted positions measured by the radiation distribution measuring instrument 3 and by the radiation polluted position measuring instrument 4, the radiation intensity of the subject 12 to be measured is calculated at a detection efficiency E determined in consideration for attenuation of gamma-rays inside the subject 12 to be measured, and is evaluated.
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公开(公告)号：JPH09236670A
公开(公告)日：1997-09-09
申请号：JP4391096
申请日：1996-02-29
Applicant: TOSHIBA ENGINEERING CO , TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI , BABA MITSUO
IPC: G01T3/00
Abstract: PROBLEM TO BE SOLVED: To construct simply an equipment structure for executing installation of a radiation source easily and quickly by positioning the radiation source at a measuring position set in the vicinity of a sensor for neutron detection, on the occasion of calibration, and at a base position set for the occasion other than the calibration and by controlling transfer and positioning of the radiation source, and thereby to improve the operability sharply. SOLUTION: A radiation source 10 is transferred to a measuring position Y set in the vicinity of a neutron sensor 5, on the occasion of calibration, and to a base position X set for the occasion other than the calibration. In order to position the radiation source to the measuring position Y and the base position X, a radiation source moving part 20 is provided. The transfer and positioning of the radiation source 10 are controlled by a radiation source control means 25. According to this constitution, an equipment structure for executing installation of radiation source easily and quickly is constructed simply and thereby the operability is improved, while a disadvantageous state of affairs in terms of a radiation control, such as external and internal exposures of an operator, can be avoided without fail.
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公开(公告)号：JPH0921877A
公开(公告)日：1997-01-21
申请号：JP16895195
申请日：1995-07-04
Applicant: TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI
Abstract: PROBLEM TO BE SOLVED: To provide a radioactivity evaluation device of waste with high efficiency and high accuracy by conducting radioactivity analysis of various properties of waste exhausted from a nuclear facility in a generating source or in a treating process, and conducting the radioactivity analysis by radiation measurement or measurement of the number of atoms. SOLUTION: A radioactivity evaluation device comprises a sampling means 6 which samples part of waste exhausted from a waste treating process 5, an analyzing means 7 which analyzes radioactivity of a radioactive nuclide in the sample, a measuring means 8 of the amount of waste contained in solidified waste, a measuring means 9 of the amount of a solidifying agent contained in the solidified waste, an input means 10 which inputs data of radioactivity of the radioactive nuclide, the amount of waste, and the amount of solidifying agent, a calculation means 11 which calculates radioactivity of the radioactive nuclide contained in the solidified waste from input data, and an output means 12 which displays radioactivity of the radioactive nuclide contained in the waste.
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公开(公告)号：JPH0735868A
公开(公告)日：1995-02-07
申请号：JP18030693
申请日：1993-07-21
Applicant: TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI , SAKURAI JIRO
Abstract: PURPOSE:To allow simultaneous measurement of the distribution of radioactive contamination due to alpha, beta and gamma-rays on a large or irregular surface to be measured using a single equipment. CONSTITUTION:Sheet holders 4a, 4b for holding and housing a radiation measuring sheet 1 and an anticontamination sheet 3 individually are fixed to a telescopic arm 5 which is secured to a supporting base 6. A mechanism 11 for driving the telescopic arm 5 and the sheet holders 4a, 4b, an equipment securing means 8, an equipment moving mechanism 9, an operating circuit 10, and a recording/transmitting means 11 are mounted on the supporting base 6. The radiation measuring sheet 1 is provided with a polymer compound layer containing a stimulable phosphor emission substance. The plane to be measured is covered with the radiation measuring sheet 1 and left as it is for a predetermined time thus storing the radiation energy. It is then irradiated with a pumping light and the emission is read out and processed thus determining the point and concentration of contamination.
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公开(公告)号：JP2000121790A
公开(公告)日：2000-04-28
申请号：JP29261798
申请日：1998-10-14
Applicant: TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI , YOSHIZAWA HIROYASU , OZAWA TAMOTSU
Abstract: PROBLEM TO BE SOLVED: To provide a transportation method for nuclear fuel perfectly maintaining nuclear fuel rods even falling of a transportation cask in transporting a plurality of fuel rods in bundle by using a transportation cask. SOLUTION: In this nuclear fuel rod transporting method, a nuclear fuel rod packing body 40 is loaded in an inner vessel 2 in the nuclear fuel rod transportation cask 30. A spacer 7 consisting of hard material member or a shock absorbing member is inserted in the gap between the inner wall of the inner vessel 2 and the upper and lower ends of the nuclear fuel rod packing body 40 so as to load in the state that the gap at the lower end on the nuclear fuel rod packing body 40 is eliminated.
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Patent Agency Ranking
公开(公告)号：JPH11258350A
公开(公告)日：1999-09-24
申请号：JP5694298
申请日：1998-03-09
Applicant: TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI , NITSUTOU KOUICHI
IPC: G01T1/169
Abstract: PROBLEM TO BE SOLVED: To provide a non-contact surface contamination inspection device and method for inspecting surface contamination without contact and without damaging a paint film that is painted on a base material to be inspected and a surface to be inspected, for reducing such secondary waste as a filter and a filter where a contaminant as seen in a conventional contamination inspection adheres to, and for preventing a contamination area from spreading. SOLUTION: A contaminant 3 adhering to the surface of an inspection target 2 is allowed to leave the inspection target 2 in the form of fine particles due to the application of laser beams from a laser beam application means 4, the eliminated contaminant 3 is directly captured by a solid capturing member 18, radiation that is emitted from the captured contaminant 3 is measured by a radiation measuring means 20, the surface contamination site and the surface contamination density of the inspection target 2 are inspected without any contact, and the contaminant 3 adhering to the capturing member 18 is allowed to leave by a capturing member reproduction means 24 for reproducing the capturing member 18 after the measurement of radiation is completed.
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公开(公告)号：JPH07151879A
公开(公告)日：1995-06-16
申请号：JP30164293
申请日：1993-12-01
Applicant: TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI
Abstract: PURPOSE:To enhance economy by decreasing the amount of tritium produced from lithium and to alleviate the amount of the waste of the tritium and the radiation exposure on works and environments as a result. CONSTITUTION:A helium gas recovery system 16 and a helium gas circulating system 17 are connected, and the helium-gas circulating system 17 is connected to a blanket 6. Helium-3, which is a disintegrated product of tritium, generated in a tritium storing gas system 1 and a tritium-waste treatment system 13, is recovered by a helium-gas recovery system 16. Helium-4 (alpha-particle), which is generated by the nuclear fusion reaction of tritium conveyed through an exhaust-gas purifying system 8 and deuterium and the nuclear reaction of the lithium and neutrons, is recovered by the helium-gas recovery system 16. The helium-3 in the recovered helium gas is sent into a blanket 6 from the helium- gas circulating system 17. The helium-3 reacts with the blanket 6 around core plasma 5 and neutron, and tritium is reproduced and recovered.
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公开(公告)号：JPH0534462A
公开(公告)日：1993-02-09
申请号：JP19004091
申请日：1991-07-30
Applicant: TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI , KATO KEIICHIRO
Abstract: PURPOSE:To achieve high efficiency and to minimize the amount of radiation exposure of workers so as to make it possible to see whether radioactive waste is a contaminant or an activated material by comparing the measured value of beta-rays with that of 7-rays. CONSTITUTION:A remarkable difference is caused between the ratio of the counting rate of beta rays 4 detected by a beta-ray detector 2 to that of gamma-rays 5 detected by a gamma-ray detector 1 when a subject 3 is a contaminant with its contaminated surface directly opposite to a measuring head H and that when the measuring head Ha is directly opposite to the opposite side of the subject 3. When the subject 3 to be measured is an activated material, no difference is caused between the ratio of the counting rate of beta-rays to gamma-rays no matter on which side the measuring is carried out. This is utilized in discriminating between contamination and activation and therefore the efficiency of work is enhanced without decontaminating or remeasuring the subject 3 to be measured and the safety of the work is secured.
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9.发明专利
公开(公告)号：JPH10288670A
公开(公告)日：1998-10-27
申请号：JP9779497
申请日：1997-04-15
Applicant: TOSHIBA CORP
Inventor： NITSUTOU KOUICHI , FUKAZAWA TAKUJI , TAMURA TOSHIYUKI , YAMAGUCHI YASUSHI , MATSUI MASAO
Abstract: PROBLEM TO BE SOLVED: To inspect the surface contamination of an object to be inspected without damaging a protection film such as a base material and a paint film and without expanding a contamination site. SOLUTION: A non-contact surface contamination inspection device 10 or a surface-treating device supports a head unit 15 so that it can travel relatively and freely for an inspection target 11. The head unit 15 is connected to a unit box via a flexible connection means. On the other hand, the head unit 15 has a laser beam irradiation means 19 for applying laser beams for inspecting surface to the object surface of the inspection target 11, a filter-capturing means 35 for detecting a bloom that left the object surface, and a bloom detection means 31 for detecting the captured bloom. In this case, a signal that is detected by the bloom detection means 31 is processed to specify the surface contamination site of the inspection target 11 and determine a surface contamination density with a dry method without any contact.
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公开(公告)号：JPH10185843A
公开(公告)日：1998-07-14
申请号：JP35096196
申请日：1996-12-27
Applicant: TOSHIBA CORP
Inventor： FUKAZAWA TAKUJI , TAMURA TOSHIYUKI
IPC: G01N23/204
Abstract: PROBLEM TO BE SOLVED: To provide a hydrogen content monitor that can quantitatively determine, in a non-destructive manner, hydrogen contained in a metal waste being measuring object, which has radio activity and of which material is not clearly known. SOLUTION: The monitor 10 houses an object to be measured 14 in an internal closed space 13 and comprises a neutron reflector 12, which, is of such material as not containing hydrogen, a neutron source 16 provided in the closed space 13 in the neutron reflector 12, a neutron detector 11 provided in the closed space 13 in the neutron reflector 12, and a signal processing device 20, which signal-processes the neutron detection signal detected with the neutron detector 11, and, relating to the neutron detector 11, the object to be measured 14 is irradiated with fast neutrons from the neutron source 16, and the neutrons decelerated and scattered by the object 14 are measured, so that the hydrogen content of an object to be measured is quantitatively analyzed in a non- destructive manner.
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