| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 21 | Neutron dosimeter including a step wedge formed of an alpha-attenuating material | US3604931D | 1969-12-10 | US3604931A | 1971-09-14 | KASTNER JACOB; OLTMAN BILLIE G |
| A neutron dosimeter includes a material which emits alpha particles when bombarded with neutrons, a plastic foil in position to intercept these alpha particles and a step wedge of a material, capable of attenuating the alpha particles, disposed between the alpha-emitting material and the plastic foil. The step wedge varies from zero thickness to such a thickness as will attenuate the most energetic alpha particles formed in the dosimeter to particles having an energy such that the particles form tracks in the plastic foil. Following exposure to neutrons the plastic foil is etched to expose the alpha tracks in the plastic. The location of the tracks in the plastic indicates the energy of the neutrons and the total number of tracks in the plastic indicates the intensity of the neutron flux.
|
||||||
| 22 | System for assaying solutions containing alpha-emitting isotopes using track-registration material | US3569703D | 1968-02-26 | US3569703A | 1971-03-09 | ALTER HENRY WARD |
| A method for determining the quantity of an alpha-emitting ingredient in a solution. A sheet of track-registration material is brought into close proximity to the solution, held there for given period of time, and then removed. This material has the characteristic of forming damage tracks along paths traversed by alpha particles. These paths may be enlarged and made visible by treatment with a suitable etchant which enlarges the tracks. The number of tracks formed in a given area is an indication of the quantity of the alpha-emitting ingredient present in the solution.
|
||||||
| 23 | Track registration alpha autoradiography | US3493751D | 1966-06-17 | US3493751A | 1970-02-03 | DAVIES JOHN H; RUIZ CARL P; STORMS HOWARD A |
| 24 | Track-etch neutron radiography | US3457408D | 1966-12-12 | US3457408A | 1969-07-22 | ALTER HENRY WARD |
| 25 | Process and detector for indicating the tracks of alpha particles using stacked layers of material | US53968466 | 1966-04-04 | US3418472A | 1968-12-24 | EVANS ROBLEY D |
| 26 | Radiation detection sheet material having metal coating to facilitate read-out | US59249266 | 1966-11-07 | US3415993A | 1968-12-10 | FLEISCHER ROBERT L; PRICE PAUL B; WALKER ROBERT M |
| 27 | A METHOD OF AUTOMATICALLY COUNTING FISSION TRACKS | EP07784679 | 2007-07-25 | EP2044463A4 | 2016-12-28 | GLEADOW ANDREW JOHN WARD |
| The present invention relates generally to the task of automatically counting the fission track density in a prepared crystal. Two images are captured by a charged coupled device (CCD) (16) attached to a microscope (14). The first or reflected light image (18) is of the surface of the crystal (12), the light captured by the CCD (16) having been reflected from the crystal surface. The reflected light image (18) is a RGB image of a prepared crystal of mica (12) containing surface voids corresponding to etched fission tracks. The second or transmitted light image (24) is of a plane near the surface of the crystal (12). The transmitted lighting image (24) is generally the same view as the reflected light image (18). A fission track void can be detected by comparing the reflected light (18) and the transmitted light (24) images. This comparison of the reflected light and the transmitted light images is best achieved using a computer software program, although this can also be done by a person comparing the images side by side or visually superimposing one on top of the other. | ||||||
| 28 | Electroplating method for producing ultralow-mass fissionable deposits | EP87303792.3 | 1987-04-29 | EP0256618B1 | 1992-12-30 | Ruddy, Francis Henry |
| 29 | Dosimeter for radon and radon daughter products | EP88300809.6 | 1988-02-01 | EP0280416B1 | 1991-05-29 | Wheeler, Robert Vincent |
| 30 | Method for permanently recording high neutron fluence | EP87307305.0 | 1987-08-18 | EP0260816B1 | 1990-12-27 | Ruddy, Francis Henry |
| 31 | Dosimeter for radon and radon daughter products | EP88300809.6 | 1988-02-01 | EP0280416A1 | 1988-08-31 | Wheeler, Robert Vincent |
An improved radon detector has an enclosed housing 12 with a removeable cap 20 to provide a chamber 18 within which a detector member 28, 30 is mounted for detecting the impact of alpha particle emissions from radon gas entering the chamber 18 through apertures 24 formed in the cap 20. The detector member 28, 30 has at least one planar surface for detecting the emissions and is supported within the chamber 18 to orient the planar detection surface in a generally vertical plane parallel to the central axis of the upstanding enclosed wall 16 which positions the detection surface in parallel opposition to preferably the major portion of the enclosing wall 16 on which radioactive decay products from radon are deposited. |
||||||
| 32 | Method for permanently recording high neutron fluence | EP87307305.0 | 1987-08-18 | EP0260816A1 | 1988-03-23 | Ruddy, Francis Henry |
A method for producing a high fluence neutron dosimeter which serves as a permanent record for fission rate measurement wherein an alpha-emitting source which is a radioactive parent of the daughter isotope of interest is used to implant recoil ions resulting from alpha decay into a substrate such as a mica solid state track recorder which is then exposed to neutrons, etched, and both the induced fission tracks and recoil ion tracks are counted. As a result, the fission rate in fissions per atom can be calculated. |
||||||
| 33 | Method for correcting for isotope burn-in effects in fission neutron dosimeters | EP87303390.6 | 1987-04-16 | EP0256616A1 | 1988-02-24 | Gold, Raymond; McElroy, William Nordell |
A method for correcting for the effect of isotope burn-in in fission neutron dosimeters wherein two quantities are measured in order to quantify the "burn-in" contribution, namely PZ.A, the amount of (Z', A') isotope that is burned-in, and FZ.A, the fissions per unit volume produced in the (Z', A') isotope. To measure PZ. 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. Pz, 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 PZ',A' since the thermal neutron cross section is known. Fz 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, BZ',A' from these observations, the neutron field must generally be either time independent or a separable function of time t and neutron energy E. |
||||||
| 34 | A METHOD AND APPARATUS FOR DETECTING ALPHA-EMITTING SUBSTANCES | EP81901492.9 | 1981-06-05 | EP0052636B1 | 1985-10-02 | MALMQVIST, Erik Lennart; KRISTIANSSON, Krister |
| Method for detecting and measuring alpha-emitting substances, such as radon and/or daughter products of radon, by registering nuclear tracks on a detector. By conducting away during measuring any electrostatic field which may have built up on the detector, there is eliminated the risk of erroneous information being obtained with respect to the dosage of radiation received. A device in the form of a dosimeter for carrying out the detecting and measuring method is also provided in accordance with the invention. Arranged on or in the immediate vicinity of the registering surface (1) of the detector is an electrically conductive material (2) which at least partially covers the registering surface. In a preferred embodiment, the dosimeter may include at least one absorber (4) arranged between the registering surface and the electrically conductive material. The electrically conductive layer suitably has a constant potential and may be connected to the ground or to a source of electric voltage. | ||||||
| 35 | 높은 중성자 유속량을 영구 기록하기 위한 방법 | KR1019870008641 | 1987-08-06 | KR1019950012217B1 | 1995-10-16 | 프란시스헨리루디 |
| 내용 없음. | ||||||
| 36 | 분열 중성자 조사선량계에서 동위원소 버언-인(Burn-In)효과에 대하여 보정하기 위한 방법 | KR1019870004354 | 1987-05-04 | KR1019950001735B1 | 1995-02-28 | 레이먼드골드; 윌리암노들매크엘로이 |
| 내용 없음. | ||||||
| 37 | 초저질량의 핵분열성 퇴적물을 제조하기 위한 전기도금방법 | KR1019870003712 | 1987-04-17 | KR1019940007869B1 | 1994-08-26 | 프란시스헨리루디 |
| 내용 없음. | ||||||
| 38 | NOVEL RADIATION DETECTOR | US13988885 | 2011-11-28 | US20130234033A1 | 2013-09-12 | Steven John Stanley; John Paul Owen 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) analysing 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. | ||||||
| 39 | NOVEL RADIATION DETECTOR | US12742200 | 2008-11-14 | US20110017924A1 | 2011-01-27 | Steven Stanley; Simon John Doran; Paul Michael Jenneson |
| The invention provides a device for the detection and mapping of radiation, the device comprising a polymeric core located within an external shell material, wherein the polymeric core comprises at least one radiation sensitive component and the external sheath comprises a collimation sheath. Preferably, the polymeric core comprises a spherical core which is encased within the external shell. The external shell is preferably comprised of a metal, most preferably lead or 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; and (e) analysing said polymeric core by means of an optical analysis technique applying a software-based image reconstruction algorithm in order to determine the location, form and intensity of said radiation. 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 radio-logical hazards in 3 dimensions in sites such as active cells, gloveboxes, other active plants and confined spaces. Advantages over the prior art include 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. | ||||||
| 40 | Radon daughter dosemeter | US966469 | 1992-10-26 | US5223439A | 1993-06-29 | Rainer Rolle |
| The invention provides a radon daughter dosemeter made up of a cyclone, a filter in a filter holder and a radiation detector spaced from the filter. The filter is arranged to filter dust and aerosol particles from air issuing from the air outlet of the cyclone, and the detector is arranged to detect radiation from dust and aerosol particles on the filter. The invention also provides a method of monitoring radiation exposure of persons; and an electrochemical etching cell for the etching of detectors used in the dosemeter. | ||||||
