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1. 发明专利

JP2000258539A APPARATUS AND METHOD FOR DETECTION OF RADIATION 失效
公开(公告)号：JP2000258539A
公开(公告)日：2000-09-22
申请号：JP6342499
申请日：1999-03-10
申请人： TOSHIBA CORP
发明人： NITSUTO KOICHI , MAKINO SHUNICHIRO , TAMURA TOSHIYUKI , TAKAHARA TAKESHI , SAITO AKIHISA , KOYAIZU EIJI
IPC分类号： G01T1/20 , C09K11/00 , C09K11/56 , C09K11/61 , C09K11/68 , C09K11/78 , C09K11/79 , C09K11/80 , C09K11/82 , C09K11/84 , G01T1/202
摘要： PROBLEM TO BE SOLVED: To obtain an apparatus and a method, for the detection of a radiation, in which the required number of high-cost devices such as photodetectors is reduced, in which a structure can be made simple and in which a position can be detected. SOLUTION: A scintillator 2 in which the color of light 3 to be emitted by responding to a radiation 1 is different according to the incident position of the radiation 1 is provided. In addition, a light detecting means 20 which detects the color of the light 3 emitted from the scintillator 2 is provided. The light detecting means 20 is constituted of a color filter 4 and a photodetector 5. The radiation is made incident on the scintillator 2 in which the color of the light emitted by responding to the radiation is different according to the incident position of the radiation. The color of the light emitted from the scintillator 2 is detected by the light detecting means 20. Therefore, the incident position of the radiation on the scintillator can be detected, the required number of high-cost devices such as photodetectors is reduced, and the structure of this radiation detecting apparatus can be simplified.

2. 发明专利

JPH11109036A ALPHA-RADIOACTIVITY MEASUREMENT METHOD AND DEVICE THEREFOR 失效
公开(公告)号：JPH11109036A
公开(公告)日：1999-04-23
申请号：JP26953897
申请日：1997-10-02
申请人： TOSHIBA CORP
发明人： SANO AKIRA , TAMURA TOSHIYUKI , WADA MIKIO
IPC分类号： G01T1/16
摘要： PROBLEM TO BE SOLVED: To easily and accurately measure the α-radioactivity of an α-contami nated measurement object in a high γ ray field. SOLUTION: A container 2 containing a light element is provided on the side of a measurement sample 1 containing an α radioactive material of a neutron detector 5, the light element inside the container 2 and α rays cause (α, n) reaction, a generated neutron is detected and the α-radioactivity is obtained. Without directly measuring the α rays, the neutron generated by the (α, n) reaction of gas containing the light element filled around and the αrays is measured and the α-radioactivity is obtained. Between the neutron detector and the measurement sample, a γ ray shielding material (lead, iron) is installed. A neutron detection part with an additional function capable of selecting the thickness of the neutron detector 5 (He-3 (5a), BF3, B-10 lined (5B), FC) and the γ ray shielding material (lead, iron and tungsten alloy) corresponding to γ ray intensity is provided.

3. 发明专利

JPH0458184A SYSTEM FOR URANIUM ACCOUNTANCY AND METHOD FOR URANIUM ACCOUNTANCY 失效
公开(公告)号：JPH0458184A
公开(公告)日：1992-02-25
申请号：JP16854590
申请日：1990-06-28
申请人： TOSHIBA CORP
发明人： TAMURA TOSHIYUKI , MATSUDA YASUHIKO
IPC分类号： G21C17/06 , B01D59/34 , G01T1/167 , G01T3/00
摘要： PURPOSE:To hermetically determine the total quantity of uranium in a raw material without sampling by providing a neutron detector on the outer side of a hermetic cell for sepn. and enrichment and further, providing a gamma ray measuring instrument around a flow passage which carries enriched uranium and waste uranium. CONSTITUTION:The total quantity of the uranium in metal uranium is measured by the neutron detector 7 on the outer side of the hermetic cell 3 for separating and enriching the uranium. The enrichment is determined inline together with the total quantity of the uranium measured by the neutron detector 7 if the presence quantity of U is measured by the gamma ray measuring instrument 13 in the flow passages 10a, 10b which are corrected to the hermetic cell 3 and carrying the enriched uranium and waste uranium separated from the uranium raw material in accordance with the object of measurement. The uranium enrichment in the raw material is measured inline in this way while the contact with the atm. air is averted without sampling the raw material.

4. 发明专利

JPS58223006A Method and device for measuring thickness of pure zirconium liner of fuel coating pipe 失效
标题翻译：用于测量燃料涂层管的纯锆衬层厚度的方法和装置
公开(公告)号：JPS58223006A
公开(公告)日：1983-12-24
申请号：JP10620082
申请日：1982-06-22
申请人： Nippon Atom Ind Group Co Ltd , Toshiba Corp
发明人： TAMURA TOSHIYUKI , TAJIMA JIYUNICHIROU
IPC分类号： G01B15/02 , G01N23/223 , G21C17/06
CPC分类号： G01B15/02
摘要： PURPOSE:To perform nondestructive measurement, by irradiating X rays from the inside of a coating pipe, generating the characteristic X rays of component other than zirconium among the component of zircaloy, measuring the X rays by a detector, and obtaining the thickness of a linter from the relationship with the attenuation factor of the characteristic X rays. CONSTITUTION:A liner 2 comprising pure zirconium is provided on the inner surface of a coating pipe 1 comprising a zircaloy alloy. An X ray source 3 and X ray detector 4 are arranged in the coating pipe 1. An Am-241 radiation source 6, which is provided in the X ray source 3 radiates gamma rays, excites zirconium target 7, and generates characteristic KX rays 8. The rays are irradiated on the coating pipe 1 from a radiating port 5a. Then only component elements Fe, Cr, and Ni other than zirconium in the zircaloy alloy generate characteristic X rays 9. The characteristic X rays 9 are transmitted through a liner 2 and inputted in the X ray detector 4. The characteristic X rays 9 are attenuated when they are transmitted through the liner 2. Since the relationship between the attenuation factor and the thickness of the liner is known, the attenuation factor is obtained from the output of the X ray detector 4, and the thickness of the liner is obtained from this factor.
摘要翻译：目的：进行非破坏性测量，通过从涂层管内照射X射线，在锆石组分中产生除锆以外的成分的特征X射线，用检测器测量X射线，并获得短绒的厚度从与特征X射线的衰减因子的关系。构成：包含纯锆的衬里2设置在包括锆石合金的涂覆管1的内表面上。 X射线源3和X射线检测器4布置在涂覆管1中。设置在X射线源3中的Am-241辐射源6辐射伽马射线，激发锆靶7，并产生特征KX射线8 射线从辐射口5a照射在涂布管1上。然后，在锆石合金中只有组分元素Fe，Cr和Ni以外的锆产生特征X射线9.特征X射线9通过衬垫2透射并输入到X射线检测器4中。特征X射线9被衰减由于衰减因子与衬垫的厚度之间的关系是已知的，所以衰减系数是从X射线检测器4的输出获得的，并且衬垫的厚度由此获得因子。

5. 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.

6. 发明专利

JPH0875681A METHOD AND APPARATUS FOR NONDESTRUCTIVE ANALYSIS OF IODINE 失效
公开(公告)号：JPH0875681A
公开(公告)日：1996-03-22
申请号：JP21475594
申请日：1994-09-08
申请人： TOSHIBA CORP
发明人： TAMURA TOSHIYUKI , IGARASHI NOBORU , HIRAYAMA FUMIO
IPC分类号： G01N23/222
摘要： PURPOSE: To provide a device, which can be conveyed and set into an iodine adsorbing device that cannot be moved, can discriminate other components of radioactive product that coexists with the iodine and has a high analysis accuracy. CONSTITUTION: A material under inspection 1 is arranged in front of a neutron irradiating mechanism 2, and the neutrons are irradiated for the specified time. Then, the material under inspection 1 is moved to front part of a gamma-ray detecting mechanism 3 with a moving mechanism for the material under inspection. The gamma rays emitted from the material under inspection are detected and measured with a gamma-ray detector 10. The time from the end of the irradiation of the neutrons to the start of the detection of the gamma rays is set at the constant time including the moving time. Basically, cooling is performed for 10 minutes, and the attenuation for 2.4 minutes is allowed for the case of Ag-108. The gamma ray of 536KeV discharged from I-130m having the half-life of 9.16 minutes are noted, and the spectrometry measurement of the gammarays is performed.

7. 发明专利

JPH03273192A MOVING MONITOR DEVICE FOR NUCLEAR REACTOR IRRADIATED FUEL ASSEMBLY 失效
公开(公告)号：JPH03273192A
公开(公告)日：1991-12-04
申请号：JP7364090
申请日：1990-03-23
申请人： TOSHIBA CORP
发明人： YOSHIMOTO ATSUSHI , KUMANOMIDOU HIRONORI , TAMURA TOSHIYUKI
IPC分类号： G21C17/06
摘要： PURPOSE:To clearly discriminate between the fuel assembly and other high- gamma-ray emission body by providing a counting rate measuring circuit which measures the output signal of a 1st neutron detector and a 2nd neutron detector which is hardly affected by the background. CONSTITUTION:For example, three guide pipes 4 are installed in the measurement wall of a water passage through a setting tool 3. The two guide pipes 4 on both sides are affected when the background of gamma rays is high, but the 1st neutron detector 5 which has relatively high neutron detection sensitivity is inserted and arranged. Further, the 2nd neutron detector 6 which has low neutron detection sensitivity, but is hardly affected by the background of the gamma rays is inserted and arranged in the one center guide pipe 4. For example, a boron 10 lined counting tube is used as the detector 5 and a nuclear fission counting tube is used as the detector 6; and a counting rate measuring circuit is connected to the detector 5.

8. 发明专利

JPH02249960A METHOD FOR MEASURING CONCENTRATION OF ELEMENT 失效
公开(公告)号：JPH02249960A
公开(公告)日：1990-10-05
申请号：JP1410489
申请日：1989-01-25
申请人： TOSHIBA CORP
发明人： KAWAI AKIO , TAMURA TOSHIYUKI , TSUNODA AKIO
IPC分类号： G01N23/06
摘要： PURPOSE:To effectively utilize measurement data and to improve the accuracy of an analysis by calculating the power value to be substd. with an unfixed coefft. in such a manner that a model function attains a optimum regression curve function and determining the concn. of the element to be measured. CONSTITUTION:The term having the mass absorption coefft. of the element to be measured which is the constant intrinsic to every energy of photons or the product of the total sectional areas of the photons and the concn. of the element to be measured which is the unfixed coefft. is subtracted from the term which does not contain the concn. of the element to be measured and is continuous and smooth with the energy of the photons. The value to be substd. with the unfixed coefft. is calculated in such a manner that the model function attains the optimum regression curve function with respect to the relative count rate or relative transmittance measured with the resulted difference as the model function and the energy of the photons transmitting the measuring sample contg. the element to be measured as a parameter.

9. 发明专利

JPH02114160A NUCLEAR SUBSTANCE ANALYZER 失效
公开(公告)号：JPH02114160A
公开(公告)日：1990-04-26
申请号：JP26704888
申请日：1988-10-25
申请人： NIPPON ATOMIC IND GROUP CO , TOSHIBA CORP
发明人： SHIGENO HIROSHI , TAMURA TOSHIYUKI
IPC分类号： G01N23/02 , G01N23/222 , G21C17/06
摘要： PURPOSE:To enable the determination of a concentration level of U with a relatively short-time measurement and accurately by obtaining a ratio between the concentration of U and that of U obtained by a K-absorption edge analysis/fluorescent X ray analysis. CONSTITUTION:This analyzer is provided with a fissile neutron detector 3, an X-ray generator 4, transmission X-ray detector 5 and a fluorescent X-ray detector 6. Pu isotope ratio information and values of a concentration of Pu and that of Pu obtained by K-absorption edge analysis/fluorescent X-ray analysis method are subtracted from a total concentration ( Pu+241Pu+2 U) of a fissile substance obtained by an active trigger neutron method to obtain a concentration of . Thus, the concentration of U can be obtained accurate ly in a short time by determining a ratio between the concentration of and that of U obtained by K-absorption edge analysis/fluorescent X-ray analysis method.

10. 发明专利

JP2003004888A Spent fuel inspection device 审中-公开
标题翻译：空气燃料检测装置
公开(公告)号：JP2003004888A
公开(公告)日：2003-01-08
申请号：JP2001182540
申请日：2001-06-15
申请人： Central Res Inst Of Electric Power Ind , Toshiba Corp , 株式会社東芝 , 財団法人電力中央研究所
发明人： TAMURA TOSHIYUKI , GOTO TETSUO , MATSUMURA TETSUO
IPC分类号： G21C17/07 , G01T1/167 , G01T1/29 , G21C19/32 , G21F5/12
摘要： PROBLEM TO BE SOLVED: To raise detection sensitivity of gamma ray emitted by radioactive gas such as Kr-85 and improve quantification accuracy by suppressing the incidence into a detector, of background gamma ray such as scattered gamma ray to be a disturbance of measurement.
SOLUTION: A spent fuel storage vessel 1 storing spent fuel, an inspection shield body 2 covering the spent fuel storage vessel and a gamma ray detector are provided. The gamma ray radiated out of the radioactive gas to a measurement space set near the fuel in the spent fuel storage vessel is measured with the gamma ray detector through a collimator built in the shield body. In a position in the measurement space 8 excluding the region that the collimator 10 views, a gamma ray shield member 14 is provided. Nearby the wall of the spent fuel storage vessel in the region the collimator 10 views, magnetic field devices 16 and 17 for a positron reflection are placed so that the magnetic field is arranged vertical to the collimator direction.
COPYRIGHT: (C)2003,JPO
摘要翻译：要解决的问题：为了提高诸如Kr-85的放射性气体发射的γ射线的检测灵敏度，并且通过抑制入射到检测器中的诸如散射伽马射线的背景伽马射线成为测量干扰来提高定量精度。解决方案：提供储存乏燃料的乏燃料储存容器1，覆盖乏燃料储存容器的检查屏蔽体2和伽马射线检测器。通过伽马射线检测器通过内置在屏蔽体内的准直仪测量从放射性气体辐射出的伽马射线到设在废燃料存储容器内的燃料附近的测量空间。在除了准直仪10所看到的区域之外的测量空间8中的位置，设置有伽马射线屏蔽构件14。在准直器10所看到的区域中，在废燃料存储容器的壁附近，放置用于正电子反射的磁场装置16和17，使得磁场垂直于准直器方向排列。

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