| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 1 | 电子束扫描轨迹的精确测量方法 | CN201710192009.0 | 2017-03-28 | CN106918834A | 2017-07-04 | 罗立平; 刘欢; 王洪强; 高学林 |
| 本发明公开了一种电子束扫描轨迹的精确测量方法，包括以下步骤：（ⅰ）靶材的制备；（ⅱ）电子束扫描轨迹测量；（ⅲ）测量轨迹长度，建立数学关系；（ⅳ）应用验证。本发明通过对电子束扫描轨迹X轴向、Y轴向的分别测定，实现了二维平面任意扫描形状的精确控制，所提供的电子束扫描轨迹直接测量法，测量方法及测量工具简单实用，且测量精准度高，测量相对偏差小于2%。 | ||||||
| 2 | 폴더 형태의 반원형 고리가 부착된 시간적분형 라돈농도 측정기 | KR1020040017942 | 2004-03-17 | KR1020050092841A | 2005-09-23 | 박영웅 |
| 라돈은 알파선을 방출하는 방사성동위원소로써 지각에 널리 분포하고 있는 우라늄의 6번째 붕괴생성물에 해당하는, 무색, 무미, 무취의 불활성가스에 해당한다. 특히 라돈은 폐암을 유발하는 물질이라고 입증되었으며, 이에 따라 선진 외국에서는 라돈농도 측정 및 저감화를 위한 법적인 조치가 취해지고 있는 상태이다. 그러나 국내의 경우는 라돈이 자연적으로 존재하는 방사성 물질이라는 이유로 인하여 그 동안 체계적인 관리가 이루어지지 않고 있었으나, 최근 "다중이용시설등의 실내공기질관리법"의 제정 등을 계기로 법적인 관리가 이루어지게 되었다. 라돈농도 측정법으로는 시간적분형 측정법, 회분식 측정법 및 연속모니터링법으로 구분할 수 있으며, 관리의 측면에서 가장 적합한 측정법은 시간적분형 측정법이라고 알려져 있다. 본 발명은 라돈농도 관리의 목적으로 가장 널리 사용되고 있는 시간적분형 라돈농도 측정기에 있어서, 기존에 사용되는 측정기의 구조를 개선하여 휴대가 간편한 실을 이용하여 측정기를 원하는 높이로 설치할 수 있도록 하였을 뿐만 아니라 필터를 파손시키지 않고 본체 내부에 장착된 고체비적검출기를 현장에서 쉽게 교환할 수 있도록 설계한 것을 특징으로 하고 있다. | ||||||
| 3 | 고리가 부착된 시간적분형 라돈농도 측정기 | KR2020040007325 | 2004-03-17 | KR200356797Y1 | 2004-07-21 | 박영웅 |
| 라돈은 알파선을 방출하는 방사성동위원소로써 지각에 널리 분포하고 있는 우라늄의 6번째 붕괴생성물에 해당하는, 무색 무미 무취의 불활성가스에 해당한다. 특히 라돈은 폐암을 유발하는 물질이라고 입증되었으며, 오래 전부터 선진 외국에서는 라돈농도 측정 및 저감화를 위한 법적인 조치가 취해지고 있는 상태이다. 그러나 국내의 경우는 라돈이 자연적으로 존재하는 방사성 물질이라는 이유로 인하여 그 동안 체계적인 관리가 이루어지지 않고 있었으나, 최근 "다중이용시설등의 실내공기질관리법"의 제정 등을 계기로 법적인 관리가 이루어지게 되었다. 라돈농도 측정법으로는 시간적분형 측정법, 회분식 측정법 및 연속모니터링법으로 구분할 수 있으며, 관리의 측면에서 가장 적합한 측정법은 시간적분형 측정법이라고 알려져 있다. 본 고안은 라돈농도 관리의 목적으로 가장 널리 사용되고 있는 시간적분형 라돈농도 측정기에 있어서, 현장 설치시 권고된 위치에 고정시키기가 편리할 뿐만 아니라 본체 내부에 장착된 고체비적검출기를 현장에서 쉽게 교환할 수 있도록 설계한 것을 특징으로 하고 있다. | ||||||
| 4 | 장기 중성자 선량 측정 노출중 동위원소 버언-인을 검출 및 교정하는 방법 | KR1019870003711 | 1987-04-17 | KR1019950012820B1 | 1995-10-21 | 프란시스헨리루디 |
| 내용 없음. | ||||||
| 5 | 되튐 이온-착상에 의해서 원자로 중성자 선량 측정용 초저질량 분열성 부착물을 생산하기 위한 방법 | KR1019870008642 | 1987-08-06 | KR1019950012218B1 | 1995-10-16 | 프란시스헨리루디 |
| 내용 없음. | ||||||
| 6 | METHOD OF NEUTRON TOMOGRAPHY | US15748051 | 2016-07-21 | US20180209923A1 | 2018-07-26 | Malcolm Joyce; Stewart Agar; Edmund Colley; Miriam Colling; Joseph Dykes; Pheovos Kardasopoulos; Kate Mitton; Michael Aspinall |
| A method of obtaining neutron tomography images of a workpiece (201), by means of a neutron source (101) and a plurality of neutron detectors (107), where the neutron source is an isotopic source containing less than one gram of radioactive isotope(s); the workpiece is up to 300×300×300 mm in size; and measurements to generate at least one tomography image of a workpiece take one hour or less to obtain. | ||||||
| 7 | Radiation detector | US13988885 | 2011-11-28 | US08847171B2 | 2014-09-30 | Steven John Stanley; John Horsfall |
| The invention provides a device for the detection and mapping of radiation, the device comprising a polymeric core (18) located within an external shell material (1), wherein the polymeric core comprises a plurality of stacked polymeric sheets comprising at least one radiation sensitive component which is sensitive to said radiation emitted by said radioactive materials and the external sheath comprises a collimation sheath (1). Preferably, the polymeric core comprises a cubic, cylindrical, spherical or truncated spherical shape which is encased within the external shell. The external shell is preferably comprised of a metal, most preferably tungsten. The invention also provides a method for the detection and mapping of radiation in a location, which comprises: (a) placing a device according to the invention in the location to be investigated; (b) allowing the device to remain in the location and be exposed to the radiation for a predetermined length of time; (c) removing the device from the location; (d) removing the polymeric core from the external shell; (e) analyzing said polymeric core by means of an optical analysis technique applying a software-based image reconstruction algorithm to image the polymeric core; and (f) determining the location, form and intensity of said radiation by further software-based analysis. The device and method of the invention facilitate the detection and mapping of radiation, and find particular use in mapping the location, intensity and identity of radiological hazards in 3 dimensions in sites such as active cells, gloveboxes, other active plants and confined spaces. Advantages over the prior art include significantly improved radiation sensitivity, the lack of requirement for an electrical supply, and the ability to deal with high radiation backgrounds and to be deployed in confined or restricted spaces. | ||||||
| 8 | Personal gamma-ray and radon monitor | US521178 | 1990-05-09 | US5134297A | 1992-07-28 | Naomi H. Harley; Passaporn Chittaporn |
| A compact electrically conductive housing includes a plurality of access ports defined in the top section of the housing to permit radon gas (.sup.222 Rn) to diffuse into the housing. The access ports are covered by a diffusion barrier such as a layer of foam rubber sheet inside the housing. The bottom section of the housing includes an integrally molded, electrically conductive pedestal having three recessed wells therein. Two wells contain a stacked pair of an SSNTD on top of a calcium fluoride TLD. The third well contains the same components, but with the TLD on top of the SSNTD, and the TLD of this stacked pair is pre-dosed with gamma-rays. The pedestal is covered with a film of electrically neutral aluminized MYLAR (polyester film). | ||||||
| 9 | Electrostatic capture type radon measuring apparatus | US348835 | 1989-05-08 | US5029248A | 1991-07-02 | Hiroshi Miyake |
| Disclosed is an electrostatic capture type radon-measuring apparatus, which includes a supporting circular cylinder supported on a supporting table with an axis of the cylinder extending substantially vertically. A positive electrode has a curved surface extending convexly upward from the upper end of the supporting cylinder. A lower positive electrode of a truncated cone shape has open upper and lower ends and extends as narrowed downward from the upper end of the supporting cylinder. A negative electrode has an upper end thereof located in the vicinity of the lower end opening of the lower positive electrode. A solid track detector is covered with an electro-conductive thin film having .alpha. ray permeability and is mounted on the negative electrode. A cover is provided on the supporting table and encloses the supporting cylinder, upper and lower positive electrodes, negative electrode and solid track detector. The cover has an air-ventilating portion provided with a filter which does not permit the passage of daughter nuclides of radon and thoron. | ||||||
| 10 | Detector for radon | US211516 | 1988-06-24 | US4920272A | 1990-04-24 | Robert C. Yoder |
| A detector member having the property of forming damage tracks along the paths traversed by impinging alpha particles is provided with at least two opposing detection surfaces exposed on respective opposite sides of the detector member. The opposing detection surfaces enable the detector member to form damage tracks by alpha particles impinging either of the detection surfaces which are simultaneously exposed to irradiation. Conventional cellulosic film such as cellulose nitrate can be employed with both sides of the film serving as detection surfaces. The dual-surfaced film can be framed and packaged in a compact configuration convenient to use in homes or offices. The damage tracks from both of the irradiated surfaces can be simultaneously counted using preferred spark counting techniques. | ||||||
| 11 | Dosimeter for radon and radon daughter products | US12266 | 1987-02-09 | US4778992A | 1988-10-18 | Robert V. Wheeler |
| An improved radon detector has an enclosed housing with a removeable cap to provide a chamber within which a detector member is mounted for detecting the impact of alpha particle emissions from radon gas entering the chamber through apertures formed in the cap. The detector member has at least one planar surface for detecting the emissions and is supported within the chamber to orient the planar detection surface in a generally vertical plane parallel to the central axis of the upstanding enclosed wall which positions the detection surface in parallel opposition to preferably the major portion of the enclosing wall on which radioactive decay products from radon are deposited. | ||||||
| 12 | Method for detecting and correcting for isotope burn-in during long-term neutron dosimetry exposure | US897552 | 1986-08-18 | US4749866A | 1988-06-07 | Francis H. Ruddy |
| A method is described for detecting and correcting for isotope burn-in during-long term neutron dosimetry exposure. In one embodiment, duplicate pairs of solid state track recorder fissionable deposits are used, including a first, fissionable deposit of lower mass to quantify the number of fissions occuring during the exposure, and a second deposit of higher mass to quantify the number of atoms of for instance .sup.239 Pu by alpha counting. In a second embodiment, only one solid state track recorder fissionable deposit is used and the resulting higher track densities are counted with a scanning electron microscope. This method is also applicable to other burn-in interferences, e.g., .sup.233 U in .sup.232 Th or .sup.238 Pu in .sup.237 Np. | ||||||
| 13 | Method for correcting for isotope burn-in effects in fission neutron dosimeters | US897555 | 1986-08-18 | US4744939A | 1988-05-17 | Raymond Gold; William N. McElroy |
| A method is described for correcting for effect of isotope burn-in in fission neutron dosimeters. Two quantities are measured in order to quantify the "burn-in" contribution, namely P.sub.Z',A', the amount of (Z', A') isotope that is burned-in, and F.sub.Z', A', the fissions per unit volume produced in the (Z', A') isotope. To measure P.sub.Z', A', two solid state track recorder fission deposits are prepared from the very same material that comprises the fission neutron dosimeter, and the mass and mass density are measured. One of these deposits is exposed along with the fission neutron dosimeter, whereas the second deposit is subsequently used for observation of background. P.sub.Z', A' is then determined by conducting a second irradiation, wherein both the irradiated and unirradiated fission deposits are used in solid state track recorder dosimeters for observation of the absolute number of fissions per unit volume. The difference between the latter determines P.sub.Z', A' since the thermal neutron cross section is known. F.sub.Z', A' is obtained by using a fission neutron dosimeter for this specific isotope, which is exposed along with the original threshold fission neutron dosimeter to experience the same neutron flux-time history at the same location. In order to determine the fissions per unit volume produced in the isotope (Z', A') as it ingrows during the irradiation, B.sub.Z', A', from these observations, the neutron field must generally be either time independent or a separable function of time t and neutron energy E. | ||||||
| 14 | Passive dosimeter | US698792 | 1985-02-06 | US4704537A | 1987-11-03 | Manfred Urban; Hans Kiefer |
| In a passive dosimeter including a diffusion chamber having an interior space, and an alpha particle detector located within the chamber for producing an indication of the concentration of radon and thoron gas and decay products and the relative percentages of radon and thoron individually, the diffusion chamber is constructed so that the interior space is open to the outside, the size of the detector and of the interior space are selected for causing the differences in path length of alpha particles in the interior space to permit the emission energy to be determined independently of the location of decay events, and the surface of the chamber bordering the interior space is electrically conductive. | ||||||
| 15 | Dose equivalent neutron dosimeter | US222867 | 1981-01-07 | US4381454A | 1983-04-26 | Richard V. Griffith; Dale E. Hankins; Luigi Tomasino; Mohamed A. M. Gomaa |
| A neutron dosimeter is disclosed which provides a single measurements indicating the amount of potential biological damage resulting from the neutron exposure of the wearer, for a wide range of neutron energies. The dosimeter includes a detecting sheet of track etch detecting material such as a carbonate plastic, for detecting higher energy neutrons, and a radiator layer containing conversion material such as .sup.6 Li and .sup.10 B lying adjacent to the detecting sheet for converting moderate energy neutrons to alpha particles that produce tracks in the adjacent detecting sheet. The density of conversion material in the radiator layer is of an amount which is chosen so that the density of tracks produced in the detecting sheet is proportional to the biological damage done by neutrons, regardless of whether the tracks are produced as the result of moderate energy neutrons striking the radiator layer or as the result of higher energy neutrons striking the sheet of track etch material. | ||||||
| 16 | Inorganic vitreous detector material | US966825 | 1978-12-05 | USRE30141E | 1979-11-06 | Hans-Herbert Kaes |
| An inorganic vitreous detector material which in principle is composed of the three-component system consisting of metaphosphoric acid, aluminum metaphosphate, and zinc oxide, is used for the determination of the energy of particles of high energy. Such a material may additionally contain silicon dioxide and boron trioxide. | ||||||
| 17 | Reducing noise in uranium exploration | US715225 | 1976-08-18 | US4063087A | 1977-12-13 | Robert L. Fleischer |
| A method and apparatus are described for reducing or removing the background noise caused by thoron gas (.sup.220 Rn) in uranium exploration conducted by the detection of radon gas (.sup.222 Rn) emanating from the ground. This is accomplished by the use of a number of alpha particle detectors, each of which is disposed in a protective enclosure. A barrier which permits, but deliberately retards, the passage therethrough of gases is disposed in the path to be traversed before such gases can reach the alpha particle detector. The increase in the transit time made necessary by requiring soil gases to move through the barrier should be sufficiently long to allow the decay of most of the thoron, thereby eliminating its contribution to the total signal reflected at the detector. | ||||||
| 18 | Radiation detection method | US3770962D | 1971-11-01 | US3770962A | 1973-11-06 | FLEISCHER R; WALKER R |
| A process for detecting radiation damage which comprises exposing a surface of a thin sheet of a dielectric material to radiation to form tracks of radiation damaged material therein which pass through the thickness of the sheet. The sheet is then contacted with an etchant which selectively dissolves and removes the tracks of radiation damage material to form holes extending from one surface of the sheet through the opposite surface. The resulting holes are a measure of radiation damage and are detected by visual means by detecting the light which emerges from the holes on the one side of the etched sheet while the opposite side of the etched sheet is irradiated with light having a wavelength which is absorbed by the material in an amout sufficient to produce a significant contrast to the light passing through the holes.
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| 19 | Radon detection | US3665194D | 1968-12-27 | US3665194A | 1972-05-23 | ALTER HENRY WARD; PRICE PAUL B |
| A method and apparatus for detecting and monitoring radon gas and its alpha-emitting daughter products. A sheet of trackregistration material is exposed in an area to be monitored, the material having the property of forming damage tracks along paths traversed by alpha particles. After exposure, the material is etched with a reagent to enlarge the tracks, making them visible so they can be counted. The number of tracks formed during the exposure period is a measure of the amount of radon and radon daughters present in the monitored area. The invention is useful as a dosimeter to monitor mine atmospheres, and also has applications in uranium prospecting.
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| 20 | Method and apparatus for counting radiation damage tracks in sheet material using a capacitive discharge device | US82841169 | 1969-04-23 | US3663815A | 1972-05-16 | CROSS WILLIAM GUNN; TOMMASINO LUIGI |
| Fission fragment tracks produced in sheet mica and other electrical insulating materials of radiation dosimeters are counted by leaching the tracks so that they provide electrical discharge paths through the sheet, placing an aluminum foil on top of the sheet, applying a voltage between an electrode covering the underside of the sheet and the foil to sequentially puncture the foil by electrical discharges through the tracks and counting the discharges.
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