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    • 4. 发明授权
    • 방사성폐기물 드럼 TGS 분석의 기준핵종 정량분석을 위한 간섭핵종의 간섭현상 제거방법
    • 用于在TOMOGRAPHIC GAMMA扫描仪上表征主要核素的干扰校正的校准方法
    • KR101380769B1
    • 2014-04-17
    • KR1020130137572
    • 2013-11-13
    • 주식회사 고도기술
    • 정성엽전태훈
    • G01T1/36G01T1/02
    • G01T1/36G01T1/167G01T7/005G21F5/005G21F9/28
    • The present invention relates to an interference removing method of interference nuclide for quantitative analysis of standard nuclide in radioactive waste drum TGS analysis and, more specifically, an interference removing method of interference nuclide for a quantitative analysis of standard nuclide in radioactive waste drum TGS analysis, capable of maximizing accuracy on the quantitative analysis of the standard nuclide in a radioactive waste drum. The present invention includes a first step of calculating the difference between gamma-ray energy (EK) of the standard nuclide and gamma-ray energy (EI) of the interference nuclide; a second step of calculating optimal energy range factor (F(EK)); and a third step of setting final energy (EKPE) of the standard nuclide as a value in which the gamma-ray energy (EK) of the standard nuclide is added to a value in which half amplitude (FWHM(EK)) of a detector on the standard nuclide and the optimal energy range factor are multiplied. [Reference numerals] (AA) Start; (BB) End; (S102) Form a primer layer; (S104) Arrange an insulation plate; (S106) Form an insulation waterproof mortar layer; (S108) Form a waterproof mortar layer; (S110) Form a protective mortar layer; (S112) Attach a pattern sheet; (S114) Apply a pigment; (S116) Remove the pattern sheet; (S118) Forming a coating layer
    • 本发明涉及一种用于放射性废物桶TGS分析中的标准核素的干扰核素的干扰去除方法,更具体地说,涉及用于放射性废物桶TGS分析中的标准核素的定量分析的干扰核素的干扰去除方法, 能够最大限度地提高放射性废料桶中标准核素的定量分析的准确性。 本发明包括计算标准核素的γ射线能量(EK)与干扰核素的γ射线能量(EI)之差的第一步骤; 计算最佳能量范围因子(F(EK))的第二步; 以及将标准核素的最终能量(EKPE)设定为将标准核素的γ射线能量(EK)加到检测器的半幅度(FWHM(EK))的值的值的第三步骤 在标准核素上和最佳能量范围因子相乘。 (附图标记)(AA)开始; (BB)结束; (S102)形成底漆层; (S104)安排绝缘板; (S106)形成绝缘防水砂浆层; (S108)形成防水砂浆层; (S110)形成保护砂浆层; (S112)安装图案纸; (S114)涂上颜料; (S116)取下图案纸; (S118)形成涂层
    • 5. 发明公开
    • 피폭선량 계산시스템
    • 一种用于测量X射线暴露的系统
    • KR1020130123811A
    • 2013-11-13
    • KR1020120047217
    • 2012-05-04
    • (주)메디엔인터내셔날
    • 한승곤
    • G01T1/16A61B6/00
    • G01T1/16G01T7/005G06T7/0012
    • The present invention relates to a system for measuring X-ray exposure comprising: a database to which partial weights (β) according to distance information (FSD) from a focal point of an X-ray pipe to a detector and information on X-rays absorbed depending on the portions of a subject are inputted; an input part for inputting information on the subject and an amount of the X-rays with which the subject is irradiated; an edge drawing part for irradiating the X-rays to the subject and drawing an edge of the subject projected to the X-ray detector; an area calculating part for calculating the internal area of the edge drawn in the edge drawing part; and an X-ray exposure calculating part for calculating the X-ray exposure by calculating the distance information and the partial weights stored in the database, the portion information inputted in the input part, the X-ray information, and the area calculated by the area calculating part. [Reference numerals] (200) Input part;(300) Edge drawing part;(400) Valid area calculating part;(500) X-ray exposure amount calculating part
    • 本发明涉及一种用于测量X射线曝光的系统,包括:数据库,根据从X射线管的焦点到检测器的距离信息(FSD)的部分权重(β)和关于X射线照射的信息, 输入根据被检体的部分吸收的光线; 用于输入关于被摄体的信息的输入部分和被照射的X射线的量; 边缘绘制部分,用于将X射线照射到对象并绘制投射到X射线检测器的被摄体的边缘; 用于计算在边缘绘图部分中绘制的边缘的内部区域的面积计算部分; 以及X射线曝光计算部分,用于通过计算存储在数据库中的距离信息和部分权重来计算X射线曝光,输入部分中的部分信息,X射线信息和由 面积计算部分。 (附图标记)(200)输入部;(300)边缘绘制部;(400)有效区域计算部;(500)X射线曝光量计算部
    • 6. 发明授权
    • 방사성 폐기물 드럼의 방사능 량 산출 장치
    • 放射性废物废物计算放射性物质的装置
    • KR101260486B1
    • 2013-05-06
    • KR1020120018373
    • 2012-02-23
    • 한국수력원자력 주식회사
    • 강상희
    • G01T1/29G21C17/10
    • G01T1/169G01T1/02G01T1/167G01T7/005
    • PURPOSE: A device for calculating a radioactive dose of a radioactive waste drum is provided to determine the total radioactive dose of a low and intermediate level radioactive waste drum hard to measure by reflecting properties of each waste drum. CONSTITUTION: A device for calculating a radioactive dose of a radioactive waste drum comprises a first memory(110), a second memory(120), a first measuring unit(130), an estimating unit(140), a deduction unit(150), a second measuring unit(160), a first calculating unit(170), a correction unit(180), and a second calculating unit(190). The first memory stores correction factors for a radioactive distribution plate and a relevant section thereof. The second memory stores a conversion table for surface dose per unit radiation which indicates the relation between the density of each nuclide inside the radioactive waste drum and the surface dose per unit radiation. The first measuring unit measures the surface dose at 12 spots of the radioactive waste drum. The estimating unit utilizes distances between a measuring device(10) and the nuclides and the average surface dose of the 12 spots, thereby estimating positions of the nuclides inside the radioactive waste drum with a nonlinear optimization method. [Reference numerals] (10) Measuring device; (110) First memory; (120) Second memory; (130) First measuring unit; (140) Estimating unit; (150) Deduction unit; (160) Second measuring unit; (170) First calculating unit; (180) Correction unit; (190) Second calculating unit; (20) Drum
    • 目的:提供一种用于计算放射性废物鼓的放射性剂量的装置,以确定通过反映每个废物转鼓的性质来测量难以测量的低级和中级放射性废料桶的总放射性剂量。 构成:用于计算放射性废物桶的放射性剂量的装置,包括第一存储器(110),第二存储器(120),第一测量单元(130),估计单元(140),扣除单元(150) ,第二测量单元(160),第一计算单元(170),校正单元(180)和第二计算单元(190)。 第一存储器存储放射性分布板及其相关部分的校正因子。 第二个存储器存储每单位辐射的表面剂量的转换表,其表示放射性废物转鼓内的每个核素的密度与每单位辐射的表面剂量之间的关系。 第一个测量单位测量放射性废物桶的12个点处的表面剂量。 估计单元利用测量装置(10)和核素之间的距离和12个点的平均表面剂量,从而以非线性优化方法估计放射性废物滚筒内的核素的位置。 (附图标记)(10)测量装置; (110)第一记忆; (120)第二存储器; (130)第一测量单元; (140)估计单位; (150)扣除单位; (160)第二测量单元 (170)第一计算单元; (180)校正单元; (190)第二计算单元; (20)鼓
    • 8. 发明公开
    • 방사선원 고정식 방사선 조사기
    • 固定源类型辐射系统
    • KR1020100040628A
    • 2010-04-20
    • KR1020080099855
    • 2008-10-10
    • 한국표준과학연구원
    • 이철영하석호김현문전국진
    • G01T1/02G01T1/00G01N23/00
    • G01T7/005G01T1/02G21F5/04
    • PURPOSE: A radiation source fixing type irradiator is provided, which can achieve simplification of the whole structure of an irradiator. CONSTITUTION: A radiation source fixing type irradiator comprises an irradiator main body(10), a shielding shutter(20), a pivotal loader(30), a fixing cover(40), and a shielding cap(70). In the front of the pivotal loader mounting groove of the irradiator main body, a shutter path is formed. The internal space of the irradiator main body is filled with shielding material(16). The shielding shutter is inserted into the shutter path. The shielding shutter opens and closes the travel route of the radiation.
    • 目的:提供一种辐射源固定型照射器,其可以实现辐照器整体结构的简化。 构成:辐射源固定型照射器包括照射器主体(10),屏蔽遮板(20),枢转装载机(30),固定盖(40)和屏蔽盖(70)。 在照射器主体的枢转装载机安装槽的前部形成有快门路径。 照射器主体的内部空间填充有屏蔽材料(16)。 屏蔽快门插入快门路径。 屏蔽快门打开和关闭辐射的行进路线。
    • 9. 发明公开
    • 이동식 중성자 계측장치
    • 运输中性计数器设备
    • KR1020080076032A
    • 2008-08-20
    • KR1020070015428
    • 2007-02-14
    • 한국원자력연구원한국수력원자력 주식회사
    • 강희영김호동정정환박광준이병철주준식송대용
    • G01T3/00G01T3/02G01T3/06
    • G01T3/008G01T7/005G21C17/108
    • A transportable neutron counter device is provided to calculate a count rate of neutrons by taking into consideration energy emitted through the reaction of neutrons and He-3 gas. A transportable neutron counter device(100) includes a neutron detector(110), a signal processing unit(120), and an output unit(130). The neutron detector absorbs neutrons existing in atmosphere. The neutron detector generates electricity by using the absorbed neutrons. The signal processing unit measures a count rate of the neutrons based on the intensity of the electricity. The output unit displays the count rate. The neutron detector employs a tube containing He-3 in order to efficiently absorb the neutrons. The signal processing unit supplies power to another element.
    • 通过考虑到通过中子和He-3气体的反应发射的能量,提供了可运输的中子计数装置来计算中子的计数率。 运输中子计数器装置(100)包括中子检测器(110),信号处理单元(120)和输出单元(130)。 中子探测器吸收大气中存在的中子。 中子检测器通过使用吸收的中子发电。 信号处理单元根据电力的强度来测量中子的计数率。 输出单元显示计数率。 中子检测器采用含有He-3的管,以有效地吸收中子。 信号处理单元向另一个元件供电。
    • 10. 发明公开
    • 방사선 검출기 및 He-3 가스 누출 검출 방법
    • 具有内部泄漏检测的HE-3 NEUTRON比例计数器及相关方法
    • KR1020080005114A
    • 2008-01-10
    • KR1020070067699
    • 2007-07-05
    • 제너럴 일렉트릭 캄파니
    • 웨이스만에릭엠클라케루카스엘윌리암스제임스알앤더슨토마스알
    • G01T1/00G01T1/16
    • G01T3/00G01T1/185G01T7/005G21C17/10G01T3/001G01T3/008
    • A He-3 neutron proportional counter with internal leakage detection and a related method are provided to achieve early detection by lowering pressure in a detector and thereby increasing an alpha peak when a He-3 gas leaks. A He-3 neutron proportional counter(10) with internal leakage detection includes a cylindrical housing(12), an electrode wire(20), and a plurality of circuit connectors(40,42). The housing has a cylindrical wall and sealing parts(14,16) at both ends. The electrode wire extends through the center of the housing apart from the cylindrical wall. A detector gas is pressurized in the housing. The circuit connector is connected to the electrode wire and the housing in order to apply an electric potential. The electrode wire is made of a material providing an alpha particle to ionize the detector gas in the housing.
    • 提供具有内部泄漏检测和相关方法的He-3中子比例计数器,以通过降低检测器中的压力来实现早期检测,从而当He-3气体泄漏时增加α峰。 具有内部泄漏检测的He-3中子比例计数器(10)包括圆柱形壳体(12),电极线(20)和多个电路连接器(40,42)。 壳体具有圆柱形壁和两端的密封部分(14,16)。 电极线延伸穿过壳体的中心与圆柱形壁分开。 检测器气体在壳体中被加压。 电路连接器连接到电极线和壳体以施加电位。 电极线由提供α粒子的材料制成,以将壳体中的检测器气体电离。