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CN112593081B - 一种含钚活性炭中钚的浸取方法 - Google Patents

一种含钚活性炭中钚的浸取方法 Download PDF

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CN112593081B
CN112593081B CN202011240417.7A CN202011240417A CN112593081B CN 112593081 B CN112593081 B CN 112593081B CN 202011240417 A CN202011240417 A CN 202011240417A CN 112593081 B CN112593081 B CN 112593081B
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plutonium
activated carbon
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CN112593081A (zh
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乔淑霞
孔雪艳
靳小军
陈忠恭
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404 Co Ltd China National Nuclear Corp
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    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B7/00Working up raw materials other than ores, e.g. scrap, to produce non-ferrous metals and compounds thereof; Methods of a general interest or applied to the winning of more than two metals
    • C22B7/006Wet processes
    • C22B7/007Wet processes by acid leaching
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    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/04Obtaining plutonium
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
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Abstract

本发明属于核设施退役及三废治理技术领域,具体涉及一种含钚活性炭中钚的浸取方法。称取含钚活性炭样品于塑料萃取管中;加入硝酸溶液震荡离心分相;取上清液加入闪烁液,充分摇匀后,于液体闪烁计数器上测量。本发明使活性炭中90%以上的钚转移至水相中。

Description

一种含钚活性炭中钚的浸取方法
技术领域
本发明属于核设施退役及三废治理技术领域,具体涉及一种含钚活性炭中钚的浸取方法。
背景技术
在核科学技术试验、反应堆乏燃料后处理、军工核设施退役、核泄漏事故应急处理等过程中会产生较多的超铀长寿命α废物,这些α废物种类繁多,有金属类废物、非金属不可燃类废物、非金属可燃类废物。目前国内外对于α废物的处理缺乏相应的技术手段,仍以暂存为主,这无疑会造成资源的浪费,因为长寿命α废物中存在着可回收利用的核武器装备重要原料,如钚即可作为核反应堆燃料(MOX)和核武器的裂变物质原料,亦可作为航母、潜艇、航天火箭等的燃料。
对于α残留废物——活性炭中富集回收钚的文献国内外鲜有报道,仅有的可用于指导钚回收的文献均为典型的高放废液分离流程及核燃料后处理工艺流程中钚的萃取分离,萃取分离对象为液体,对于固体活性炭中钚的回收未见报道,对于钚回收工艺研究,钚的萃取分离可引用高放废液分离流程及核燃料后处理工艺流程中钚的萃取分离方法,但怎么使活性炭中的钚转移至水相中是首要解决的技术难点。
发明内容
本发明的目的在于提供一种含钚活性炭中钚的浸取方法,使活性炭中90%以上的钚转移至水相中。
为达到上述目的,本发明所采取的技术方案为:
一种含钚活性炭中钚的浸取方法,
称取含钚活性炭样品于塑料萃取管中;
加入硝酸溶液震荡离心分相;
取上清液加入闪烁液,充分摇匀后,于液体闪烁计数器上测量;
含钚活性炭浸取率的计算公式
Figure BDA0002768253420000021
式中:θ—含钚活性炭中钚的浸取率,单位%;
c0—浸取前含钚活性炭样品中钚的放射性活度浓度,单位Bq/g;
c—浸取后浸取液中钚的放射性活度浓度,单位Bq/mL;
m—含钚活性炭样品的质量,单位g;
v—浸取液体积,单位mL。
称取0.8g~1.0g含钚活性炭样品于50mL塑料萃取管中。
加入30mL 2.5mol/L的硝酸溶液震荡15min离心分相。
取0.20mL上清液加入10mL闪烁液,充分摇匀后,于液体闪烁计数器上测量。
本发明所取得的有益效果为:
放射性α废物中,有可回收利用的核武器重要原材料如钚,钚—239可作为核反应堆燃料(MOX)和核武器裂变物质原料,亦可作为航母、潜艇、航天火箭等的燃料;钚—238可通过衰变释放能量,是深空探测的动力来源。另外,因放射性α废物的半衰期长、生物危害大,对环境危害极大,因此,回收或处理军工核设施运行、检修、退役等过程中产生的α废物废,实现α废物中钚等核素再利用和废物降级,为α废物的处理处置提供一种可行的处理措施。
采用本方法浸取α残留废物——活性炭中钚90%以上的钚转移至水相中,解决了钚回收工艺研究中活性炭样品预处理过程。
具体实施方式
下面结合具体实施例对本发明进行详细说明。
本发明所述含钚活性炭中钚的浸取方法包括以下步骤:
称取0.8g~1.0g含钚活性炭样品于50mL塑料萃取管中;
加入30mL 2.5mol/L的硝酸溶液震荡15min离心分相;
取0.20mL上清液加入10mL闪烁液,充分摇匀后,于液体闪烁计数器上测量;
含钚活性炭浸取率的计算公式
Figure BDA0002768253420000031
式中:θ—含钚活性炭中钚的浸取率,单位%;
c0—浸取前含钚活性炭样品中钚的放射性活度浓度,单位Bq/g;
c—浸取后浸取液中钚的放射性活度浓度,单位Bq/mL;
m—含钚活性炭样品的质量,单位g;
v—浸取液体积,单位mL。

Claims (2)

1.一种含钚活性炭中钚的浸取方法,其特征在于:
称取含钚活性炭样品于塑料萃取管中;其中,称取0.8g~1.0g含钚活性炭样品于50mL塑料萃取管中;
加入硝酸溶液震荡离心分相;其中,加入30mL 2.5mol/L的硝酸溶液震荡15min离心分相;
取上清液加入闪烁液,充分摇匀后,于液体闪烁计数器上测量;
含钚活性炭浸取率的计算公式
Figure FDA0003864799790000011
式中:θ—含钚活性炭中钚的浸取率,单位%;
c0—浸取前含钚活性炭样品中钚的放射性活度浓度,单位Bq/g;
c—浸取后浸取液中钚的放射性活度浓度,单位Bq/mL;
m—含钚活性炭样品的质量,单位g;
v—浸取液体积,单位mL。
2.根据权利要求1所述的含钚活性炭中钚的浸取方法,其特征在于:取0.20mL上清液加入10mL闪烁液,充分摇匀后,于液体闪烁计数器上测量。
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US5154899A (en) * 1991-06-28 1992-10-13 Sturcken Edward F Metal recovery from porous materials
FR2688336B1 (fr) * 1992-03-03 1994-05-13 Matieres Nucleaires Cie Gle Procede pour separer le niobium, l'antimoine et/ou au moins un element des groupes viib et viii a partir de solutions aqueuses issues du retraitement des combustibles nucleaires uses.
FR2688337B1 (fr) * 1992-03-05 1994-05-13 Commissariat Energie Atomique Procede de dissolution du bioxyde de plutonium au moyen de radicaux oh. produits par radiolyse de l'eau, utilisable pour le traitement des fines de dissolution et des dechets plutoniferes.
FR2690557B1 (fr) * 1992-04-23 1994-10-21 Cogema Procédé de dissolution du plutonium et/ou d'autres éléments radioactifs présents dans des produits solides ou liquides et dispositif de chauffage par micro-ondes pour mettre en Óoeuvre ce procédé.
CN103103369B (zh) * 2011-11-14 2014-03-05 中国原子能科学研究院 一种硝酸体系中钚的催化氧化方法
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CN105110487B (zh) * 2015-09-06 2017-10-31 中国人民解放军63653部队 一种酸性废水中钚的微生物去除及回收方法
CN109735711A (zh) * 2018-12-27 2019-05-10 中核四0四有限公司 一种混凝土中钚的浸取方法
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