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    • 2. 发明公开
    • 방사선 차폐재를 이용한 원자력 전지
    • 使用辐射屏蔽材料的原子细胞
    • KR1020140098897A
    • 2014-08-11
    • KR1020130010872
    • 2013-01-31
    • 한국원자력연구원
    • 박창제이병철
    • G21H1/04G21F1/00
    • G21H1/04G21F1/00
    • The present invention relates to an atomic cell and, more particularly, to an atomic cell which can be semi-permanently used by using a radiation source with a relatively long half-life period and generates electricity with a semiconductor method. The atomic cell using a radiation shielding material includes the radiation source which emits gamma rays, a first shielding material which is formed on one side of the radiation source and generates electricity by the interaction with the gamma rays, and a second shielding material which is formed on the other side of the radiation source and generates electricity by the interaction with the gamma rays. According to this configuration, the atomic cell shields the radiation emitted from the radiation source through a semiconductor device and generates electricity by using the radiation at the same time. Also, electric energy is supplied by using an energy source of a small electric device by reducing the size of the atomic cell.
    • 本发明涉及一种原子电池,更具体地说,涉及一种可以通过使用半衰期较长的辐射源半永久使用并通过半导体方法发电的原子电池。 使用辐射屏蔽材料的原子电池包括发射γ射线的辐射源,形成在辐射源的一侧并通过与γ射线的相互作用产生电力的第一屏蔽材料和形成的第二屏蔽材料 在辐射源的另一侧,通过与γ射线的相互作用产生电力。 根据该结构,原子单元通过半导体装置遮蔽从辐射源发射的辐射,并通过同时使用辐射发电。 此外,通过减小原子电池的尺寸,通过使用小型电子装置的能量源来提供电能。
    • 4. 发明公开
    • 금속 핵연료 회수를 위한 개량된 전해환원용 다공성 UO2 소결펠렛의 제조방법 및 이에 따라 제조되는 다공성 UO2 소결펠렛
    • 用于生产用于电动过程的多孔UO2烧结颗粒的改进方法和多孔UO2烧结颗粒
    • KR1020130118496A
    • 2013-10-30
    • KR1020120041411
    • 2012-04-20
    • 한국원자력연구원한국수력원자력 주식회사
    • 나상호송대용김기홍
    • G21G1/00G21F1/00
    • G21C3/044G21C19/42G21C21/02G21C2003/045Y10S376/903
    • PURPOSE: An improved method for manufacturing a porous uranium dioxide (UO2) sintered pellet for electrolytic reduction in order to collect metallic nuclear fuel and the porous UO2 sintered pellet manufactured by the same are provided to uniformly distribute the different concentrations of fissionable materials inside the spent nuclear fuel, thereby improving accuracy in measuring the fissionable materials. CONSTITUTION: An improved method for manufacturing a porous uranium dioxide (UO2) sintered pellet for electrolytic reduction in order to collect metallic nuclear fuel includes: a step of forming powder including triuranium octoxide (U3O8) with oxidizing the spent nuclear fuel including UO2; a step of homogenizing the powder including U3O8; a step of manufacturing a formed body with forming the homogenized powder; and a step of sintering the formed body, and then forming the porous UO2 sintered pellet with reducing the sintered body in a reducing atmospheric gas. [Reference numerals] (AA) Sintered density (%T.D.); (BB) Sintering condition; (CC) Sintering temperature (°C)
    • 目的:提供一种用于制造用于电解还原的多孔二氧化铀(UO2)烧结颗粒以收集金属核燃料的改进方法和由其制造的多孔UO2烧结颗粒,以将不同浓度的可裂变材料均匀分布在已用 核燃料,从而提高测量可裂变材料的准确性。 构成:为了收集金属核燃料而制造用于电解还原的多孔二氧化铀(UO2)烧结颗粒的改进方法包括:形成包括三氧化铀(U3O8)在内的粉末的步骤,其中包括氧化废废核燃料; 使包含U3O8的粉末均质化的步骤; 形成均匀粉末的成形体的工序; 以及烧结成形体的步骤,然后在还原性气氛中还原烧结体形成多孔UO2烧结颗粒。 (标号)(AA)烧结密度(%T.D。); (BB)烧结条件; (CC)烧结温度(℃)
    • 5. 发明公开
    • 방사선 발생원의 방향 측정이 가능한 방사선 측정장치
    • 一种能够检测辐射源方向的辐射探测器
    • KR1020100069255A
    • 2010-06-24
    • KR1020080127896
    • 2008-12-16
    • 한국원자력연구원
    • 장지호조용섭
    • G21C17/06G21F1/00
    • G01T1/167G21C17/06G21F3/00
    • PURPOSE: A radiation measuring apparatus is provided to measure the dose of radiation by rotating a radiation shielding part along the outer periphery of a radiation detector. CONSTITUTION: A radiation measuring apparatus comprises a radiation detector(100), a radiation shielding part(110), a driving part, a display part or a storage part. The radiation detector measures the dose of radiation. The radiation shielding part has a cylindrical shape. The radiation shielding part surrounds the radiation detector. An opening(112) is formed in one side of the radiation shielding part. The driving part controls the rotation of the radiation shielding part. The display part or the storage part displays or stores the dose of radiation and a direction of radiation source.
    • 目的:提供辐射测量装置,通过沿辐射探测器的外周旋转辐射屏蔽部分来测量辐射剂量。 构成:辐射测量装置包括辐射检测器(100),辐射屏蔽部分(110),驱动部分,显示部分或存储部分。 辐射检测器测量辐射剂量。 辐射屏蔽部分具有圆柱形状。 辐射屏蔽部分围绕辐射检测器。 在辐射屏蔽部分的一侧形成开口(112)。 驱动部控制辐射屏蔽部的旋转。 显示部分或存储部分显示或存储辐射剂量和辐射源的方向。
    • 7. 发明公开
    • 중성자 차폐재
    • NEUTRON屏蔽材料
    • KR1020060070505A
    • 2006-06-23
    • KR1020060046313
    • 2006-05-24
    • 히타치 지이 뉴클리어 에너지 가부시키가이샤
    • 가모시다마모루오다마사시니시다까시이가기미노리시미즈마사시
    • G21F1/00
    • G21F1/10C08L63/08
    • 본 발명은, 약 150∼200℃의 고온 환경하에서 장기간 사용해도 수소 밀도의 저하가 거의 없는 고분자 재료에 의한 중성자 차폐재를 제공한다.
      가열 경화형 에폭시 수지를 채용한다. 주제(主劑)는 비스페놀 A형 에폭시 수지를 비롯한 각종 에폭시 수지, 경화제는 지환식 폴리아민, 폴리아미드 아민, 방향족 폴리아민, 산무수물 등을 이용한다. 이들을 혼합하고, 실온 보다도 높은 온도에서 경화시킨다. 난연성을 부여하는 경우에는 수산화 마그네슘 등의 난연제를 첨가하고, 중성자 차폐 성능을 높이는 경우에는 중성자 흡수재를 첨가한다. 또, 중성자의 감속능을 높이는 경우에는 수첨 비스페놀 A형 에폭시 수지를 주제로 하거나, 수소화 금속 또는 수소 흡장 합금을 첨가한다. 본 중성자 차폐재는 장기간에 걸쳐 고온 환경하에 있어서도 수소수밀도(水素數密度)가 저하하지 않으므로 중성자 차폐 성능이 저하하지 않고 유효한 차폐재로서 기능한다.
    • 高分子中子屏蔽材料,当长时间暴露于150〜200℃的高温时,几乎不降低氢气密度。使用热固型环氧树脂。 基础树脂选自各种环氧树脂如双酚A型环氧树脂。 固化剂选自脂环族多胺,聚酰胺胺,芳香族多胺,酸酐等。 这些材料在高于室温的温度下混合并硬化。 为了赋予硬化树脂耐火性,向混合物中加入阻燃剂如氢氧化镁。 为了改善硬化树脂的中子屏蔽性能,向混合物中加入中子吸收材料。 此外,为了提高调节性能,使用氢化双酚A环氧树脂作为基础树脂,或添加金属氢化物或吸氢合金。 本中子屏蔽材料作为重要的中子屏蔽材料起作用,因为其氢数密度在高温条件下长时间不会下降,并且中子屏蔽性能不下降。
    • 8. 发明授权
    • 엑스-선 흡수 물질 및 변형체
    • 엑스 - 선흡수물질및변형체
    • KR100450247B1
    • 2004-09-24
    • KR1020007003445
    • 1998-09-24
    • 노소브 이고르 스테파노비치
    • 노소브이고르스테파노비치다카첸코블라디미르이바노비치이바노프발레리아나톨리에비치페첸킨발레리이바노비치소코로프스타니슬라브유리비치
    • G21F1/00
    • G21F1/106G21Y2002/10G21Y2004/10Y10T442/259Y10T442/2607Y10T442/2926Y10T442/2975Y10T442/2992Y10T442/3382Y10T442/3455Y10T442/3976Y10T442/475Y10T442/654Y10T442/658Y10T442/699
    • The present invention relates to an X-ray absorbing material which can be used in medicine as well as in the production of special protection clothes, protection screens, housings, protection coatings and isolation materials. In a first embodiment, the material uses as a filler a poly-dispersed kneading-segregated mixture containing metallic particles having a size of between 10 and 10 m, wherein said particles are bonded to the surface of a textile base. The density of the material is defined by the relation qN = (0.01 - 0.20)qP wherein qN is the density of the X-ray absorbing material as a whole while qP is the density of the material used for the particles of the X-ray absorbing filler. In a second embodiment, this invention uses as a filler the above-mentioned mixture though the particles are surrounded by the volume of a matrix made of a compound that solidifies under atmospheric pressure. The total mass of the poly-dispersed and segregated mixture is defined by the relation M = (0.05 - 0.5)m where M is the total mass of the X-ray absorbing poly-dispersed and segregated filler, while m is the equivalent mass of the filler material which is equal by its protection properties to the mass M. In a third embodiment, this invention uses as a filler the above-mentioned mixture though the particles we bonded to an intermediate substrate consisting of a textile base and surrounded by the volume of a matrix.
    • 本发明涉及一种可用于医药以及特殊防护服,防护网,外壳,防护涂层和隔离材料生产的X射线吸收材料。 在第一个实施方案中,该材料使用多分散的捏合 - 分离混合物作为填料,该混合物含有尺寸为10 -9〜 和10 -3。 其中所述颗粒结合到纺织品基底的表面。 材料的密度由关系式qN =(0.01-0.20)qP定义,其中qN是整个X射线吸收材料的密度,而qP是用于X射线颗粒的材料的密度 吸收填料。 在第二个实施方案中,本发明使用上述混合物作为填料,尽管颗粒被在大气压下固化的化合物制成的基体的体积所包围。 多分散和分离混合物的总质量由M =(0.05-0.5)m定义,其中M是X射线吸收多分散和分离填料的总质量,而m是 该填充材料通过其对质量M的保护性能而相等。在第三实施例中,本发明使用上述混合物作为填充剂,尽管我们粘合到由纺织品基体组成的中间基体上并且由体积 的矩阵。
    • 10. 发明公开
    • 방사선 차단용 재료및 이 재료로 된 보호장비
    • 辐射防护材料和这种材料的保护设备
    • KR1020010095618A
    • 2001-11-07
    • KR1020000018884
    • 2000-04-11
    • 하종권하재관
    • 하종권하재관
    • G21F1/00
    • PURPOSE: A radiation shielding material and protective equipment made up of such material is provided to achieve an improved radiation shielding effect. CONSTITUTION: A radiation shielding material is manufactured according to the steps of crushing the nonmetal into approximately 400 meshes, wherein the nonmetal is composed of 45 weight parts illite, 25 weight parts Pb, 0.8 weight part Py, 0.5 weight part Bi, 0.7 weight part Cu, 0.5 weight part Sn, 4 weight parts Zn, 3 weight parts Mo, 3 weight parts Ni, 2 weight parts Wo and 0.5 weight part Ti; mixing the crushed nonmetal with polyethylene; performing heat treatment to the resultant material at the temperature of 160°C; and compressing the resultant material in a mold. Protection equipment for use of person working in the field related to radiation ray, is made up of the radiation shield material made in the above-described manner. The protection equipment includes a garment, hat and gloves.
    • 目的:提供辐射屏蔽材料和由这种材料制成的保护设备,以实现更好的辐射屏蔽效果。 构成:根据将非金属粉碎至约400目的步骤制造辐射屏蔽材料,其中非金属由45重量份的伊利石,25重量份的Pb,0.8重量份的Py,0.5重量份的Bi,0.7重量份组成 Cu,0.5重量份Sn,4重量份Zn,3重量份Mo,3重量份Ni,2重量份Wo和0.5重量份Ti; 将破碎的非金属与聚乙烯混合; 在160℃的温度下对所得材料进行热处理; 并将所得材料压缩在模具中。 在与辐射有关的领域工作的人员使用的保护设备由以上述方式制成的辐射屏蔽材料组成。 保护设备包括服装,帽子和手套。