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11. 发明专利

JPH10123070A HYDROGEN CONTENT ANALYZER 失效
公开(公告)号：JPH10123070A
公开(公告)日：1998-05-15
申请号：JP27328096
申请日：1996-10-16
申请人： TOSHIBA CORP
发明人： TAMURA TOSHIYUKI , FUKAZAWA TAKUJI
IPC分类号： G01N23/222
摘要： PROBLEM TO BE SOLVED: To provide a hydrogen content analyzer which can determine hydrogen contained in a highly radioactive sample, to be measured, with an unclear material kind and with an unclear density and which uses an n.γ method. SOLUTION: A sample 1 to be measured is housed inside a neutron moderator system 2, and a neutron source 3 is arranged inside the neutron moderator system 2. A γ-ray collimator 5 and a γ-ray detector 4 which are surrounded by a γ-ray shielding material 7 are arranged so as to face the neutron moderator system 2. The sample 1 to be measured is turned and scanned. A material which contains hydrogen is not used for a neutron moderator 2c in a direction in which the γ-ray collimator 5 is anticipated, a peak to which attention is to be paid is 2.22MeV. A γ-ray filter 6 is put into the γ-ray collimator 5, and low-energy γ-rays are attemulated. The γ-ray detector 4 is formed to be of an anti-Compton type so as to remove the Compton effect and the escape peak of high-energy-γ-rays. While the counted number of γ-rays of Zr and that of γ-rays of Fe are used, a material (neutron absorption) is discriminated and corrected. By a pulsed neutron irradiation method, the S/N ratio of a hydrogen content analyzer is increased.

12. 发明专利

JPH0682559A METHOD FOR DISCRIMINATING RADIOACTIVITY OF RADIOACTIVE WASTE WHETHER IT IS DUE TO CONTAMINATION OR RADIOACTIVATION 失效
公开(公告)号：JPH0682559A
公开(公告)日：1994-03-22
申请号：JP21373391
申请日：1991-08-26
申请人： TOSHIBA CORP
发明人： FUKAZAWA TAKUJI , KATO KEIICHIRO , KOGATA SATOSHI
IPC分类号： G01T1/167 , G01T1/169 , G21F9/30
摘要： PURPOSE:To discriminate between contamination and radioactivation of radioactive waste by arranging radiation detectors one at the positions facing the opening of an object and another not facing the opening and comparing the ratio between beta- and gamma-rays, or between a scattered gamma-ray and a direct gamma-ray. CONSTITUTION:In case of an inner face contaminated object P, radiation detector 1a opposing to an opening detects direct gamma-ray of the object P more but radiation detector 1b not opposing to the opening detects scattered gamma-ray more than the detector 1a thus producing a difference in the ratio of the count of scattered gamma-ray to the count of direct gamma-ray between the detectors 1a, 1b. In case of an activated object P, both detectors 1a, 1b detect scattered gamma-ray and difference scarcely appears in the ratio of scattered gamma-ray/direct gamma-ray between the detectors 1a, 1b. Consequently, discrimination can be made between contamination and activation by comparing the ratio of scattered gamma-ray/direct gamma-ray between the detectors 1a, 1b.

13. 发明专利

JPH0666948A APPARATUS FOR INSPECTING LEAKING RATE OF RADIOACTIVE GAS 失效
公开(公告)号：JPH0666948A
公开(公告)日：1994-03-11
申请号：JP21772892
申请日：1992-08-17
申请人： TOSHIBA CORP
发明人： FUKAZAWA TAKUJI
IPC分类号： G01M3/20 , G01T1/167 , G01T7/02 , G21F9/02
摘要： PURPOSE:To measure the leaking rate of radioactive gas for every nuclide from radioactive waste by improving radioactive-gas scavenging efficiency, and performing the separate scavenging for every nuclide on one line. CONSTITUTION:A container 2 contains radioactive solid waste 1. Both ends of a circulating line 5 are connected to an exhaust port 3 and an inlet port 4 of the container 2. A radioactive-gas scavenging mechanism 6 arranged on the circulating line 5 and scavenging the radioactive gas discharged from the radioactive solid waste 2, and a gas-flow type beta-ray detector 7 arranged on the downstream side of the radioactive- gas scavenging mechanism 6 are provided. Furthermore, the following parts, that is, a gas circulating pump 8 which circulates the gas through the circulating line 5, flowmeters 9 and 10 which measure the flow rate of the circulating gas, a radiation detecting part 11 which measures the alpha ray and the beta ray of the sample of the radioactive gas scavenged by the radioactive-gas scavenging mechanism 6, a signal processing system 12 which analyzes and processes the detected signal from the radiation detecting part 11, and a radioactive-gas-leaking-rate operator 13 which computes the leaking rate of the radioactive gas of the radioactive solid waste 1 based on the output of the signal processing system 12 and the scavenging time, are provided.

14. 发明专利

JPH0527044A EVALUATION OF RADIOACTIVITY OF SOLIDIFIED RADIOACTIVE WASTE BODY 失效
公开(公告)号：JPH0527044A
公开(公告)日：1993-02-05
申请号：JP17953191
申请日：1991-07-19
申请人： TOSHIBA CORP
发明人： FUKAZAWA TAKUJI , YOSHIMURA YUKIO , YASUOKA MAKOTO
IPC分类号： G01T1/167 , G01T7/00
摘要： PURPOSE:To obtain the radioactivity evaluation method for a solidified radioactive waste body in which the absolute value of the radioactivity in each radioactive nucleus contained in the solidified radioactive waste body can be measured easily by the nondestrictive method and safety can be improved. CONSTITUTION:gamma-ray spectrum measurement is carried out by revolving a simulated glass solidified body 6, and the revolution average counting rate is measured. Then, the simulated glass solidified body 6 is shifted in the height direction, and the revolution average counting rate is measured again. The distribution of the counting rate in the height direction is obtained by repeating the shift in the height direction and the revolution measurement. Then, the detection efficiency per area at an arbitrary position in the radial direction is obtained by dividing the average counting rate in the height direction by the gamma-ray generation quantity per time of a beam source and the area occupied by a gamma-ray collimator 4 at the radius position. Then, the position in the radial direction of the beam source is changed, and the measurement and analysis are repeated, and the distribution of the detection efficiency in the radial direction is obtained, and the average detection efficiency per volume for the gamma-ray radiated from the simulated glass solidified body 6 is obtained.

15. 发明专利

JPH11183693A METHOD AND DEVICE FOR DECONTAMINATION 失效
公开(公告)号：JPH11183693A
公开(公告)日：1999-07-09
申请号：JP36713597
申请日：1997-12-25
申请人： TOSHIBA CORP , TOSHIBA ENGINEERING CO
发明人： FUKUSHIMA TADASHI , NITSUTOU KOUICHI , FUKAZAWA TAKUJI , OKAMOTO YUTAKA
IPC分类号： G21F9/28
摘要： PROBLEM TO BE SOLVED: To decontaminate surfaces of structural materials and equipment in contact with a radioactive fluid through laser irradiation while preventing radioactive adherents from scattering and suppress or reduce the readhesion of radioactivity after the decontamination. SOLUTION: A large area of a surface of an object 4 is irradiated with a laser 6 at a homogenized low energy density to remove a radioactive substance adhering to the surface by exfoliating it and suppress the readhesion of the radioactive substance through the modification of the surface of a base material. The laser irradiation can be done in water or a liquid containing chemicals such as an oxidizer and a reductant, which makes it possible both to prevent the diffusion and emission of the exfoliated radioactive substances into the air and to accelerate the modification of the surface of the base material. By using a double pulse laser or that of two or more waves, moreover, even the timing and period of each laser irradiation can be controlled through the decontamination and surface modification.

16. 发明专利

JPH10160689A HYDROGEN CONTENT ANALYZING DEVICE 失效
公开(公告)号：JPH10160689A
公开(公告)日：1998-06-19
申请号：JP31674796
申请日：1996-11-27
申请人： TOSHIBA CORP
发明人： FUKAZAWA TAKUJI , TAMURA TOSHIYUKI
IPC分类号： G01N23/204 , G21F9/02
摘要： PROBLEM TO BE SOLVED: To provide a hydrogen content analyzing device with which, in non- destructive manner and at high precision, the hydrogen mingled in a test sample is determined, even when such test sample as metal waste is radioactive and large with high density while its material (kind of metal) is not necessarily clear. SOLUTION: The device comprises a test sample 1 of radioactive material, a neutron detector 4 which measures neutron released from the sample, a neutron reflector 2 which, of material not containing hydrogen, surrounds the sample and neutron detector, and a signal processing device which processes the signal outputted from the neutron detector. The signal processing device has a function to analyses element contained in the sample based on the count value and count rate of neutron detected with the neutron detector, for obtaining hydrogen content.

17. 发明专利

JPH04370786A RADIOACTIVITY IDENTIFICATION METHOD FOR RADIOACTIVE WASTE 失效
公开(公告)号：JPH04370786A
公开(公告)日：1992-12-24
申请号：JP14735191
申请日：1991-06-19
申请人： TOSHIBA CORP
发明人： FUKAZAWA TAKUJI , KATO KEIICHIRO
IPC分类号： G01T1/167 , G01T1/169
摘要： PURPOSE:To enable identification of a radioactive pollutant and a radioactive matter without breaking an object by obtaining a correlation of a ratio of scattered gamma rays to direct gamma rays of a radioactive waste measured a plurality of planes. CONSTITUTION:A radiation detector 1 is arranged on both sides of an object 3 to be measured and the perimeter thereof is covered with a shielding container 2. A signal obtained from the detector 1 is subjected to a forward amplification 4 and a linear amplification 6 and the signal is converted 7 to digital from analog. A process memory 8 performs a signal processing to display an output with a calculator 9. gamma rays from a pollutant A with a pollutant 10 existing on the surface of the object 3 are detected/directly being little scattered by material. But when the object 3 is a radioactive matter B, radioactivity has gammarays released from the inside of the material and hence. more scattered gammarays are detected 1 as compared with the pollutant A in addition to the direct gammarays. Thus, the scattered gamma rays and the direct gamma rays of the object 3 are compared in counting ratio with detectors 1 varied in measuring position thereby enabling the identifying the pollutant A and the radioactive matter B.

18. 发明专利

JPH03285197A METHOD FOR MEASURING RADIOACTIVITY OF SOLID RADIOACTIVE WASTE 失效
公开(公告)号：JPH03285197A
公开(公告)日：1991-12-16
申请号：JP8704190
申请日：1990-03-30
申请人： TOSHIBA CORP
发明人： SANO AKIRA , FUKAZAWA TAKUJI
IPC分类号： G01T1/167 , G01T3/00
摘要： PURPOSE:To enable an accurate evaluation of radioactivity of solid radioactive wastes by comparing neutron strength calculated from a solid radioactive waste with actually measured neutron intensity of the waste. CONSTITUTION:First of all, by utilizing actually measured tau ray strength, for instance, neutron intensity emitted from an object solid radioactive waste is calculated, under the condition that radioactivity is uniform inside the solid radioactive waste. On the other hand, the intensity of neutrons emitted from alphanuclides is actually measured, too, and the both neutron intensities are compared with each other. When the both neutron intensities have the same value, it is judged that the radioactivity is uniform inside the solid radioactive waste and therefore the actually measured tau ray intensity is taken as an index showing the radioactivity of whole solid radioactive waste. When the both neutron intensities are substantially different from each other, it is judged that the radioactivity is not uniform inside the solid radioactive waste and therefore, through adjustment of the actually measured tau ray intensity, based upon difference between the both neutron intensities, a tau ray intensity when the radioactivity is uniform inside the radioactive waste, is obtained.

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