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    방사성 핵종을 포함하는 폐이온 교환수지 처리방법 및 장치
    152.
    发明授权
    방사성 핵종을 포함하는 폐이온 교환수지 처리방법 및 장치 有权
    废放射性离子交换树脂的处理方法及其装置

    公开(公告)号：KR101668727B1

    公开(公告)日：2016-10-25

    申请号：KR1020150165723

    申请日：2015-11-25

    Applicant: 한국원자력연구원

    Inventor： 양희철 ,  백민훈 ,  김형주 ,  정동용 ,  최종원

    IPC: G21F9/12 ,  G21F9/08 ,  G21F9/14

    CPC classification number: G21F9/08 ,  C02F1/42 ,  C02F11/008 ,  C02F2101/006 ,  C02F2103/023 ,  G21F9/12 ,  G21F9/16 ,  G21F9/30 ,  G21Y2002/60 ,  G21Y2004/201

    Abstract: 본발명은방사성핵종을포함하는폐이온교환수지처리방법및 장치에관한것으로, 상세하게는, 방사성핵종을포함하는폐이온교환수지를단계적열처리과정을통해처리하는방법및 이를수행하는장치에관한것이다. 본발명은단계적열처리방법을통해주 성분인탄소를가스화하지않으면서방사성핵종을휘발하여분리및 회수하는방법으로방사성핵종을포함하는폐이온교환수지를처리함으로써, 종래의소각및 유리화처리시나타났던문제인, 방사성세슘(Cs) 또는스트론튬(Sr) 을포함하는휘발성방사성핵종의휘발로나타나는배기가스공정내 침적오염문제및 대기로배출되는문제, 이온교환기분리시방생되는고농도(수천 ppm 이상)의 SO및 SO가포함된배기가스발생문제및 지구온난화가스인 CO가발생문제를방지하고, 동시에휘발된방사성핵종을응축후 고정화하여처리함으로써최대한의감용효과를얻을수 있다.

    핵원자로의연료집합체에사용되는지르코늄기지합금튜브와그제조방법
    154.
    发明授权
    핵원자로의연료집합체에사용되는지르코늄기지합금튜브와그제조방법 失效

    公开(公告)号：KR100411943B1

    公开(公告)日：2004-03-20

    申请号：KR1019960002063

    申请日：1996-01-30

    Applicant: 프라마 톰 ,  꼬게마 꽁빠니 제네랄 데 마띠에르 뉘끌레르

    Inventor： 쟝-뽈마르동 ,  쟝세브내 ,  다니엘샤르께

    IPC: C22C16/00

    CPC classification number: G21C3/07 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

    Abstract: A tube, for use in a fuel canister or to guide a control rod in a nuclear reactor, is made of an alloy comprising mainly Zr plus 0.4-0.6 wt.% Sn, 0.5-0.8% Fe, 0.35-0.75% V, 0.10-0.18% O, 100-180 ppm C and 50-120 ppm Si, the alloy being completely recrystallised. Also claimed is a process for mfg. the above tube in which a cast ingot of the above alloy is forged into a bar, then heated to the beta phase and quenched in water, annealed in the alpha phase at 640-760, pref. 730 degrees C, drawn and pierced to tubular form, annealed again at 640-760, pref. 700 degrees C, and then subjected to successive cold rollings to reduce the tube wall thickness with heating to 640-760 degrees C under vacuum or inert atmosphere between rollings. Finally the tube is annealed at 560-650 degrees C. The parameter A representing the sum of heat treatments is between 10 and 10 .

    Abstract translation: 用于燃料罐或用于引导核反应堆中的控制棒的管由主要包含Zr加上0.4-0.6重量％Sn，0.5-0.8％Fe，0.35-0.75％V，0.10 -0.18％O，100-180ppm C和50-120ppm Si，合金完全重结晶。 还要求保护制造过程。 将上述合金的铸锭锻造成棒，然后加热至β相并在水中骤冷，在640-760℃下在α相中退火的上述管。 730℃，拉伸并刺穿成管状，再次在640-760℃退火。 700摄氏度，然后进行连续冷轧以减小管壁厚度，在真空或轧制之间的惰性气氛下加热至640-760摄氏度。 最后，该管在560-650℃下退火。表示热处理总和的参数A在10 -18℃之间。 和10 -16。

    핵연료집합체 지지격자의 제조방법 및 그것에 의해 제조된핵연료집합체 지지격자
    155.
    发明公开
    핵연료집합체 지지격자의 제조방법 및 그것에 의해 제조된핵연료집합체 지지격자 有权
    制造燃料组件支持网格的方法

    公开(公告)号：KR1020030038493A

    公开(公告)日：2003-05-16

    申请号：KR1020020068757

    申请日：2002-11-07

    Applicant: 미쯔비시 겐시넨료 가부시키가이샤 ,  미츠비시 쥬고교 가부시키가이샤

    Inventor： 키도토시야 ,  나카야마키미오 ,  야마구치야스나오

    IPC: G21C3/34

    CPC classification number: G21C21/00 ,  G21C3/3206 ,  G21Y2002/103 ,  G21Y2002/206 ,  G21Y2002/303 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/40

    Abstract: PURPOSE: To improve the corrosion resistance of a weld part so as to sufficiently withstand high efficiency operation. CONSTITUTION: A support grid is formed by assembling a plurality of straps in grid shape. The intersecting parts of the respective straps are welded and then subjected to recrystallization annealing. The recrystallization annealing is performed in a heat treating furnace in a vacuum or inert gas atmosphere, and as the recrystallization annealing condition, the heating temperature is set to 430-750°C and held for 0.5-24 hours. In the strap of a zircaloy, the crystal of a β-phase which is a high temperature metal phase is changed into a prior β-phase of quenched texture by quenching after welding, to lower corrosion resistance, but the prior β-phase of the quenched texture of the weld part is adjusted by recrystallization annealing afterwards to precipitate intermetallic compounds Fe, Cr in the supersaturated state, thus improving the corrosion resistance of the weld part.

    Abstract translation: 目的：提高焊接部件的耐腐蚀性，以充分承受高效率的运行。 构成：通过组装多个带状的带状形成支撑格栅。 焊接相应带的相交部分，然后进行再结晶退火。 在真空或惰性气氛中的热处理炉中进行再结晶退火，作为再结晶退火条件，将加热温度设定为430〜750℃，保持0.5〜24小时。 在锆石的带中，作为高温金属相的β相的晶体在焊接后通过淬火改变为先前的淬火组织的β相，以降低耐腐蚀性，但是先前的β相 然后通过再结晶退火调整焊接部分的淬火质地，使过饱和状态的金属间化合物Fe，Cr析出，从而提高焊接部的耐腐蚀性。

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