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1. 发明授权

KR101883895B1 방사성 폐기물을 혁신적으로 줄일 수 있는 제염방법 및 이를 위한 키트 有权
公开(公告)号：KR101883895B1
公开(公告)日：2018-08-02
申请号：KR1020160132373
申请日：2016-10-12
申请人： 한국원자력연구원
发明人： 박상윤 , 원휘준 , 김선병 , 최왕규 , 최만수 , 정종헌 , 윤인호 , 문제권 , 정준영 , 박정순
IPC分类号： G21F9/00 , G21F9/10
CPC分类号： G21F9/004 , C23G1/02 , C23G1/081 , C23G1/10 , C23G1/106 , G21F9/06 , G21Y2002/60 , G21Y2004/10
摘要： 본발명은황산(HSO)을포함하는화학제염제로방사능오염된금속또는합금을포함하는객체를제염처리하고, 이후발생하는제염폐액에 Ba 또는 Sr 양이온과수산화이온또는할로겐음이온의염을투입하여 Ba 또는 Sr의침전물을형성시키는제염방법을제공한다. 또한, 본발명은방사능오염된금속또는합금을포함하는객체를제염처리하기위해황산(HSO)을포함하는화학제염제및 제염하는과정에서발생하는제염폐액에이를투입하여침전물을형성하기위한 Ba 또는 Sr 양이온과수산화이온또는할로겐음이온과의염을포함하는제염처리용키트를제공한다.

2. 发明授权

KR101776860B1 원자로 노심의 잉여반응도를 평탄화시키기 위한 가연성 흡수봉 有权
公开(公告)号：KR101776860B1
公开(公告)日：2017-09-11
申请号：KR1020160048406
申请日：2016-04-20
申请人： 한국전력 국제원자력대학원대학교 산학협력단
发明人： 박진하 , 하창주
IPC分类号： G21C7/04
CPC分类号： Y02E30/39 , G21C7/04 , G21Y2002/201 , G21Y2004/10 , Y02E30/32
摘要： 본발명은노심잉여반응도평탄화를위한새로운가연성흡수봉에관한것이다. 본발명은원자로노심에서출력분포, 감속재온도계수, 잉여반응도제어의목적으로사용되는가연성흡수봉에있어서, 중앙에위치하는제1중성자흡수체(10)와동축상에서일정한거리를두고배치되는제2중성자흡수체(40) 사이에서동축상으로안내관(30)이제1공기층(20)을두고배치되고, 상기제2중성자흡수체(40)의외주면에는피복관(60)이제2공기층(50)을두고동축상에형성되어, 상기제1중성자흡수체(10)와제2중성자흡수체(40)가이중의구조로되는가연성흡수봉과; 중앙에위치하는중성자흡수체와동축상에서일정한거리의공기층(20a)을두고피복관(30a)이배치되어중성자흡수체가단일층구조로되는가연성흡수봉을포함하여주기초(Beginning of Life)부터주기말(End of Life)까지핵연료집합체의잉여반응도를일정한수준으로유지함으로써, 원자로의노심에서잉여반응도의평탄화를가능하게하는것이다.

3. 发明公开

KR1020130087763A 노심감시 및 노심보호용 하이브리드 노내계측기 집합체 有权
标题翻译：混合检测器总成用于核心监测和保护
公开(公告)号：KR1020130087763A
公开(公告)日：2013-08-07
申请号：KR1020120008884
申请日：2012-01-30
申请人： 한국수력원자력 주식회사
发明人： 차균호 , 신호철 , 노경호 , 최유선 , 배성만 , 전황용
IPC分类号： G21C17/06
CPC分类号： G21C17/10 , G21C9/00 , G21Y2002/206 , G21Y2004/10
摘要： PURPOSE: A hybrid in-furnace measurement instrument group for core monitoring and core protection is provided to more accurately measure a state of core by using vanadium measurement instrument and platinum measurement instrument. CONSTITUTION: A platinum measurement instrument (130) performs a core protection function. A vanadium measurement instrument performs a core monitoring function. A background measurement instrument (120) performs the core monitoring function. A core exit thermocouple (140) is integrated into one. The vanadium measurement instrument consists of five numbers of vanadium measurement instruments.
摘要翻译：目的：提供核心监测和核心保护的混合炉内测量仪组，通过使用钒测量仪器和铂测量仪器更准确地测量核心状态。规定：铂金测量仪器（130）执行核心保护功能。钒测量仪器执行核心监控功能。背景测量仪器（120）执行核心监控功能。芯出口热电偶（140）被集成到一个中。钒测量仪器由五个钒测量仪器组成。

4. 发明公开

KR1020130035534A 파형강판을 이용한 원전격납구조물 有权
标题翻译：使用波形钢板的核反应堆混凝土容器
公开(公告)号：KR1020130035534A
公开(公告)日：2013-04-09
申请号：KR1020110099884
申请日：2011-09-30
申请人： 연세대학교 산학협력단
发明人： 김상효 , 최문석
IPC分类号： G21C13/02 , G21F7/00
CPC分类号： Y02E30/40 , G21C13/093 , G21Y2002/30 , G21Y2004/10
摘要： PURPOSE: A nuclear containment structure using a corrugated steel plate is provided to reduce a building cost and the weight of the structure and to enhance space occupancy by increasing a second section moment by using a liner member of a corrugated shape formed by bending a flat member. CONSTITUTION: A liner member(10) is formed into a corrugated shape having repeatedly arranged furrows and floors. A horizontal reinforcing member(20) increases combination force between the liner member and a concrete wall and is horizontally connected along an outer surface of the liner member. A first support unit is connected with the floors of the liner member and a combination unit is connected with the bottom of the first support unit. A second support unit is connected with an end of the combination unit and protruding in an upper direction.
摘要翻译：目的：提供使用波纹钢板的核容纳结构，以减少建筑成本和结构的重量，并且通过使用通过弯曲平坦构件形成的波纹形状的衬垫构件来增加第二截面力矩来增加空间占用。构成：衬套构件（10）形成为具有反复布置的沟槽和地板的波纹形状。水平加强构件（20）增加了衬套构件和混凝土壁之间的组合力，并且沿衬套构件的外表面水平连接。第一支撑单元与衬套构件的地板连接，组合单元与第一支撑单元的底部连接。第二支撑单元与组合单元的一端连接并沿上方突出。

5. 发明公开

KR1020120031523A 핵 반응기 동작 방법 및 펠릿／피복의 손상을 감소시키기 위한 특정 펜슬형 피복 합금을 사용하는 방법 无效
标题翻译：用于操作核反应堆的方法和使用特定的PENCIL CLADDING合金来减少颗粒/层压损伤
公开(公告)号：KR1020120031523A
公开(公告)日：2012-04-03
申请号：KR1020127005137
申请日：2004-06-01
申请人： 아레바 엔피
发明人： 델라포이크리스틴 , 쥴리앙브루노
IPC分类号： G21C7/02
CPC分类号： G21C3/07 , G21Y2002/104 , G21Y2004/10 , Y02E30/40
摘要： 본 발명은 핵 반응기를 동작하는 방법에 관한 것으로, 여기서, 조립체는 핵 연료봉(3)을 포함하고, 적어도 하나의 핵 연료봉은 - 0.8 내지 1.3wt%의 니오븀, 1000ppm과 1700ppm 사이의 산소를 가지는 완전히 재결정화된 지르코늄계 합금으로 이루어진 피복(17)과, 우라늄 산화물 핵 연료 펠릿(23)을 포함하며, 펠릿은 피복(17)내부에 적층된다. 반응기의 동작 상태는 전력 전이 동안, 핵 연료봉(3)의 선형 전력 밀도가 임계 선형 전력 밀도 보다 낮게 유지되고, 임계 선형 전력 밀도는 430W/cm 보다 크며, 및/또는 핵 연료봉(3)의 선형 전력 밀도의 변동은 180W/cm 보다 큰 임계 변동 보다 낮게 유지되도록 제어된다.

6. 发明授权

KR101021897B1 방사선 차폐유리 및 그 제조방법 有权
标题翻译：用于制造其辐射屏蔽玻璃的方法
公开(公告)号：KR101021897B1
公开(公告)日：2011-03-18
申请号：KR1020087009633
申请日：2006-10-13
申请人： 니폰 덴키 가라스 가부시키가이샤
发明人： 쵸주켄 , 미와신키치
IPC分类号： C03C4/08 , C03C3/07 , C03C3/072
CPC分类号： C03C4/087 , C03C3/07 , C03C3/072 , G21F1/06 , G21Y2002/10 , G21Y2002/201 , G21Y2002/304 , G21Y2004/10
摘要： 질량% 표시로, 유리 조성으로서 SiO
2 10∼35%, PbO 55∼80%, B
2 O
3 0∼10%, Al
2 O
3 0∼10%, SrO 0∼10%, BaO 0∼10%, Na
2 O 0∼10%, K
2 O 0∼10%를 함유하고, 또한 두께 10㎜에 대한 파장 400㎚에 있어서의 전광선 투과율이 50%이상인 방사선 차폐유리, 또는 동일한 유리 조성으로서, 또한 PET 검사용 감마선 차폐재에 사용하는 방사선 차폐유리.
방사선 차폐유리

7. 发明公开

KR1020090018581A 원자로용 그레이 제어봉 有权
标题翻译：核反应堆鲁棒灰色控制杆
公开(公告)号：KR1020090018581A
公开(公告)日：2009-02-20
申请号：KR1020080079765
申请日：2008-08-14
申请人： 웨스팅하우스 일렉트릭 컴퍼니 엘엘씨
发明人： 포미레아누,라두오. , 혼,마이클제이. , 롱,씨.조셉 , 미스벨,마이클씨. , 스터커,데이비드엘.
IPC分类号： G21C7/10 , G21C7/00
CPC分类号： G21C7/10 , G21Y2002/104 , G21Y2002/207 , G21Y2002/303 , G21Y2004/10 , G21Y2004/30 , Y02E30/39
摘要： A control rod for a nuclear reactor is provided to reduce swelling and heat in a neutron absorbing material of a dashpot region of a fuel assembly guide thimble when inserting a gray control rod into a core of the nuclear reactor completely. A long pipe cladding(40) includes an external size to match the most narrow size inside the hollow of the control rod guide thimble of the nuclear fuel assembly. A first end plug is slidingly received in the dashpot(44). A first neutron absorbing material is larger than the received length in the dashpot or the axial distance of the first neutron absorbing material is extended through the long pipe cladding. A second neutron absorbing material has a higher reactive value than the first neutron absorbing material. A second terminal plug is finished in the second end of the long pipe cladding. The inside of the hollow of the control rod guide thimble is composed of an upper end unit receiving the control rod and a lower end unit having a reduced inner diameter part serving as the dashpot.
摘要翻译：提供了用于核反应堆的控制杆，用于当将灰色控制杆完全插入核反应堆的核心时，减少燃料组件导向套管的缓冲区区域的中子吸收材料中的膨胀和热量。长管道包层（40）包括外部尺寸以匹配核燃料组件的控制棒导向套管的空心内的最窄尺寸。第一端塞被滑动地容纳在缓冲器（44）中。第一中子吸收材料大于缓冲器中的接收长度，或者第一中子吸收材料的轴向距离通过长管包层延伸。第二中子吸收材料具有比第一中子吸收材料更高的反应性值。在长管包层的第二端中完成第二端子塞。控制杆导向套管的中空部的内部由容纳控制棒的上端单元和具有缩小的内径部的作为缓冲器的下端单元构成。

8. 发明公开

KR1020050061560A 알루미늄 합금-탄화붕소 복합재 有权
标题翻译：改进的铝合金 - 碳硼化合物复合材料
公开(公告)号：KR1020050061560A
公开(公告)日：2005-06-22
申请号：KR1020057007078
申请日：2003-10-24
申请人： 리오 틴토 알칸 인터내셔널 리미티드
发明人： 포르틴장-이베스 , 쉬히쟈케스 , 장카밀 , 브리슨폴 , 하니쉬우타 , 두터돈앨런 , 첸시아오-광
IPC分类号： C22C1/10 , B22D19/14
CPC分类号： G21C19/40 , B22C9/22 , C22C1/026 , C22C1/1036 , C22C32/0057 , C22C2001/1047 , G21F1/08 , G21Y2002/10 , G21Y2004/10
摘要： A cast composite material is prepared by furnishing an aluminum-based matrix alloy and forming a mixture of free- flowing boron carbide particles and the aluminum-based matrix alloy in molten form which is stirred to wet the matrix alloy to the boron carbide particles and to distribute the particles throughout the volume of the melt. The molten mixture is then cast. The fluidity of the molten mixture is maintained by (a) maintaining the magnesium content of the matrix metal below about 0.2 % by weight, or (b) starting with a matrix metal containing less than 0.2 % by weight magnesium and adding further magnesium to the mixture a short time before casting, or (c) having at least 0.2 % by weight titanium present in the mixture.
摘要翻译：通过提供铝基基质合金并形成熔融形式的自由流动的碳化硼颗粒和铝基基质合金的混合物来制备铸造复合材料，所述铝基基质合金被搅拌以将基体合金润湿至碳化硼颗粒，并且将颗粒分散在整个体积的熔体中。然后浇铸熔融混合物。熔融混合物的流动性通过（a）将基质金属的镁含量维持在约0.2重量％以下来维持，或（b）从含有小于0.2重量％的镁的基质金属开始，并向镁混合物在铸造之前很短时间，或（c）在混合物中存在至少0.2重量％的钛。

9. 发明授权

KR100443482B1 방사성물질용차폐부재와그제조방법및방사성약액생성장치 失效
公开(公告)号：KR100443482B1
公开(公告)日：2004-10-06
申请号：KR1019960012079
申请日：1996-04-20
申请人： 니혼 메디피직스 가부시키가이샤
发明人： 사케이오카노 , 후미야오바타 , 메사토오하야 , 요시마사다나카
IPC分类号： G21F1/00
CPC分类号： G21F1/12 , G21F5/015 , G21Y2002/201 , G21Y2002/301 , G21Y2002/302 , G21Y2004/10 , G21Y2004/303 , G21Y2004/305 , G21Y2004/40
摘要： The present invention provides a shielding member for radioactive substance which can be made compact in size and light in weight with maintaining its shielding ability, or improve the shielding ability while being kept in the same size thereby to store a large volume of radioactivity. At the same time, the present invention provides a manufacturing method for the above shielding member and a radioactive solution-producing apparatus using the above shielding member. The radioactive substance-shielding member uses two or more kinds of radiation shielding materials of different shielding abilities. A shielding body (51) made of a shielding material of the highest shielding ability is arranged at an area (5b) which is the nearest to a radioactive source.
摘要翻译：本发明提供一种放射性物质用屏蔽部件，其在保持屏蔽性的同时能够实现小型化和轻量化，或者在保持相同大小的同时提高屏蔽能力，从而存储大量的放射性。同时，本发明提供了用于上述屏蔽部件的制造方法和使用上述屏蔽部件的放射性溶液生成装置。放射性物质屏蔽构件使用两种或更多种屏蔽能力不同的放射线屏蔽材料。由最高屏蔽能力的屏蔽材料制成的屏蔽体（51）布置在最靠近放射源的区域（5b）处。＆lt;图像＆GT;

10. 发明授权

KR100423109B1 핵반응기연료집합체용지르코늄-기지합금튜브및상기튜브의제조방법 失效
标题翻译： 핵반응기연료집합체용지르코늄 - 기지합금튜브및상기튜브의제조방법
公开(公告)号：KR100423109B1
公开(公告)日：2004-05-31
申请号：KR1019970704983
申请日：1996-01-26
申请人： 프라미뜸 , 꼬게마 꽁빠니 제네랄 데 마띠에르 뉘끌레르
发明人： 마르동쟝-뽈 , 세브나쟝 , 샤르께다니엘
IPC分类号： G21C3/07
CPC分类号： G21C3/07 , G21Y2002/103 , G21Y2004/10 , G21Y2004/201 , Y02E30/40
摘要： PCT No. PCT/FR96/00137 Sec. 371 Date Jul. 29, 1997 Sec. 102(e) Date Jul. 29, 1997 PCT Filed Jan. 26, 1996 PCT Pub. No. WO96/24140 PCT Pub. Date Aug. 8, 1996A tube of zirconium-based alloy for constituting all or a portion of a cladding or guide tube for a nuclear fuel assembly. The tube is made of an alloy containing, by weight, 1.0-1.7% of tin, 0.55-0.80% of iron, 0.20-0.60% total of chromium and/or vanadium, and 0.10-0.18% of oxygen, with 50-200 ppm of carbon and 50-120 ppm of silicon. The alloy further contains only zirconium and unavoidable impurities, and it is completely recrystallized.
摘要翻译： PCT No.PCT / FR96 / 00137 Sec。 371日期1997年7月29日Sec。 102（e）日期1997年7月29日PCT申请日1996年1月26日PCT Pub。 WO 96/24140 PCT Pub。日期：1996年8月8日一种锆基合金管，用于构成核燃料组件的全部或部分包层或导管。该管由含有重量百分比为1.0-1.7％的锡，0.55-0.80％的铁，0.20-0.60％的铬和/或钒以及0.10-0.18％的氧的合金制成，其中50-200 ppm的碳和50-120ppm的硅。该合金仅含有锆和不可避免的杂质，完全再结晶。

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