-
公开(公告)号：JPH0553384B2
公开(公告)日：1993-08-09
申请号：JP18927689
申请日：1989-07-21
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , MITO MASAYASU
-
公开(公告)号：JPH0551872B2
公开(公告)日：1993-08-03
申请号：JP29229787
申请日：1987-11-19
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , MITO MASAYASU
-
公开(公告)号：JPH05134049A
公开(公告)日：1993-05-28
申请号：JP29745391
申请日：1991-11-13
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , MITO MASAYASU , ONO TAKESHI
IPC: G01T3/00
Abstract: PURPOSE:To obtain a simple, light-weight neutron-done-equivalent detector which can measure the dose equivalent in the energy range of 9 digits from thermal neutron to fast neutron, and can measure the dose equivalent section for each energy. CONSTITUTION:A cylindrical rmoderator 24 comprising polyethylene or the like is mounted in a hollow cylindrical thermal neutron detector 20 so that the moderator 24 can be freely removed and attached. Furthermore, a thermal- neutron absorbing layer 26 for limiting the incident rate of the thermal neutron is arranged around the thermal neutron detector 20. The arriving thermal neutron in flying directly enters into the thermal neutron detector 20 and detected. The speeds of epi-thermal neutron and fast neutron are reduced with the moderator 24. The epi-thermal neutron and the fast neutron are made to be the thermal neutrons, which are inputted into the thermal neutron detector 20 and detected. The moderator 24 is divided into the first hollow cylindrical moderator and the second moderator, which is mounted into the hollow cylindrical part so that second moderator is freely removed and attached. Only the epi-thermal neutron is made to be the thermal neutron and can be detected by removing the second moderator.
-
公开(公告)号：JPH055783A
公开(公告)日：1993-01-14
申请号：JP15898891
申请日：1991-06-28
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , MITO MASAYASU , KUMAZAWA HIROKI
Abstract: PURPOSE:To obtain the detector capable of simply measuring a neutron absorption dose becoming the basis of the evaluation of the dose equivalent of a neutron according to a direct reading system within a real time. CONSTITUTION:A collection electrode 22 is arranged in an external electrode 20 and an absorbing layer 24 (rubber containing boron B) limiting the transmission of a thermal neutron in a constant ratio is arranged on the side of the neutron incident surface of a thermal neutron detector sealed with nuclear reaction gas. A deceleration material 26 composed of polyethylene and an absorbing layer 28 are arranged on the side of the emitting surface of the thermal neutron detector and a proton recoil scintillation detector 28 is further arranged. A part of a thermal neutron transmits through the absorbing layer 24 to reach the thermal neutron detector to be detected. An epithermal neutron is decelerated by the deceleration material 26 to be converted to a thermal neutron and reaches the thermal neutron detector to be detected thereby. A fast neutron is detected by the proton recoil scitillation detector 30.
-
公开(公告)号：JPH0364844A
公开(公告)日：1991-03-20
申请号：JP20207889
申请日：1989-08-02
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , MITO MASAYASU
Abstract: PURPOSE:To enable arbitrary measurement of either dose equivalent or exposure by mounting a measuring cap and a compensating cap on the respective entrance window portions of a GM measurement detection portion and a GM compensation detection portion to attach and detach the measuring and compensating caps. CONSTITUTION:With a GM measurement detection portion 22 and a GM compensation detection portion 24, a measuring cap 20 which meets the conversion curve of dose equivalent in a low energy region at measuring the dose equivalent and a compensating cap 25 which limits exposure in a low energy region with sensitivity characteristics obtained from the GM compensation detection portion 24 are mounted on entrance windows 22a, 24a. At measuring exposure, the measuring cap 20 is mounted on the entrance window portion 22a only of the GM measurement detection portion 22 to operate and output an output difference from the result of radiation detection of each detection portion. Accordingly, the conversion curve of dose equivalent or the characteristics of exposure can be obtained. It is thus possible to perform arbitrary measurement and direct reading of either dose equivalent or exposure.
-
Patent Agency Ranking
公开(公告)号：JPH0282187A
公开(公告)日：1990-03-22
申请号：JP23577988
申请日：1988-09-19
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , MITO MASAYASU
Abstract: PURPOSE:To read a dosage equivalent directly by providing a 1st detection part which has a current collecting electrode, a partition plate which is positioned opposite the reverse surface of the incidence window of the 1st detection part, a 2nd detection part, and a measurement part which measures only an electron beam. CONSTITUTION:The 1st detection part 22 is formed by using, for example, mica for the incidence window 26 provided to a 1st ionizing box and the mica is coated with carbon conductive paint to form an electrode. The window 26 is supported and fixed by a cylindrical box shape 28 which becomes the case of both detection parts 22 and 24 and an application electrode 30-1 is provided in the ionizing box of the window 26. Further, the current collecting electrode 32-1 is provided on the partition plate 34 on the reverse surface opposition side of the window 26 and insulated electrically from the electrode 30-1. The 2nd detection part 24 is provided across the detection part 22 and plate 34, and this plate 34 is made of beryllium, etc., of, for example, about 3mm and a beta-ray cutting layer and a layer which transmits gamma rays by >=90%. The thickness of the plate 34 is set to a value with which beta rays of up to 2 MeV energy can be cut off so that no beta rays reaches the detection part 24. A current detected by an electrode 32 is supplied to an electrometer 20 to measure the dosage equivalent.
-
公开(公告)号：JPS61155981A
公开(公告)日：1986-07-15
申请号：JP27644284
申请日：1984-12-28
Applicant: ALOKA CO LTD , ASAHI CHEMICAL IND
Inventor： SATO HIROO , MAEKAWA HIROSHI , MITO MASAYASU , EBISAWA MIKIO , KAGEURA YOSHIAKI
IPC: G01T1/167
Abstract: PURPOSE:To conserve the consumption amount of purge gas, by dehumidifying purge gas after the measurement of the concn. of tritium was completed to again use the same as the gas for measuring the concn. of tritium. CONSTITUTION:Tritium detection air 100 is supplied to the detection air passage of a membrane separator 10 and dried purge gas 200 is supplied to a purge gas passage. The concn. of tritium in air 100 is measured from tritium water taken in the purge gas within the membrane separator 10. A dehumidification recirculation route 50 contains a dehumidifier 52, to which the purge gas passed through an ionization box 46 is guided, and a pump 54 and perfectly dehumidifies the purge gas to reutilize the same as the purge gas 200.
-
公开(公告)号：JPH09318759A
公开(公告)日：1997-12-12
申请号：JP13338796
申请日：1996-05-28
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , ONO TAKESHI , MITO MASAYASU
IPC: G01T3/00
Abstract: PROBLEM TO BE SOLVED: To make it possible to obtain total equivalent dose by measuring equivalent dose at each neutron energy range and adding them. SOLUTION: A detector 10 has a fast neutron detector 18, an intermediate speed neutron detector 16 and thermal neutron detectors 14A, 14B. Fast neutron is detected by utilizing recoiling, the intermediate speed neutron is transformed to thermal neutron by a moderator layer 44 and detected. The neutrons are individually detected at respective energy ranges. The layer 44 is utilized only for detecting the intermediate speed neutron.
-
公开(公告)号：JPH0560074B2
公开(公告)日：1993-09-01
申请号：JP15127285
申请日：1985-07-11
Applicant: ALOKA CO LTD
Inventor： MITO MASAYASU , MAEKAWA HIROSHI
-
公开(公告)号：JPH0553396B2
公开(公告)日：1993-08-09
申请号：JP23577988
申请日：1988-09-19
Applicant: ALOKA CO LTD
Inventor： SATO HIROO , MITO MASAYASU
-
-
-
-
-
-
-
-
-
Search Results
55
records
(took 0.019 seconds)
