CN112593081A - 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

Info

Publication number
CN112593081A
CN112593081A CN202011240417.7A CN202011240417A CN112593081A CN 112593081 A CN112593081 A CN 112593081A CN 202011240417 A CN202011240417 A CN 202011240417A CN 112593081 A CN112593081 A CN 112593081A
Authority
CN
China
Prior art keywords
plutonium
activated carbon
containing activated
leaching
shaking
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN202011240417.7A
Other languages
English (en)
Other versions
CN112593081B (zh
Inventor
乔淑霞
孔雪艳
靳小军
陈忠恭
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
404 Co Ltd China National Nuclear Corp
Original Assignee
404 Co Ltd China National Nuclear Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 404 Co Ltd China National Nuclear Corp filed Critical 404 Co Ltd China National Nuclear Corp
Priority to CN202011240417.7A priority Critical patent/CN112593081B/zh
Publication of CN112593081A publication Critical patent/CN112593081A/zh
Application granted granted Critical
Publication of CN112593081B publication Critical patent/CN112593081B/zh
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • 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
    • CCHEMISTRY; METALLURGY
    • 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
    • Y02PCLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00Technologies related to metal processing
    • Y02P10/20Recycling

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Geology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Manufacturing & Machinery (AREA)
  • Environmental & Geological Engineering (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Measurement Of Radiation (AREA)

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 (4)

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;
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 FDA0002768253410000011
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:称取0.8g~1.0g含钚活性炭样品于50mL塑料萃取管中。
3.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:加入30mL 2.5mol/L的硝酸溶液震荡15min离心分相。
4.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。
CN202011240417.7A 2020-11-09 2020-11-09 一种含钚活性炭中钚的浸取方法 Active CN112593081B (zh)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202011240417.7A CN112593081B (zh) 2020-11-09 2020-11-09 一种含钚活性炭中钚的浸取方法

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202011240417.7A CN112593081B (zh) 2020-11-09 2020-11-09 一种含钚活性炭中钚的浸取方法

Publications (2)

Publication Number Publication Date
CN112593081A true CN112593081A (zh) 2021-04-02
CN112593081B CN112593081B (zh) 2023-01-03

Family

ID=75182778

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202011240417.7A Active CN112593081B (zh) 2020-11-09 2020-11-09 一种含钚活性炭中钚的浸取方法

Country Status (1)

Country Link
CN (1) CN112593081B (zh)

Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5154899A (en) * 1991-06-28 1992-10-13 Sturcken Edward F Metal recovery from porous materials
CN1078923A (zh) * 1992-03-03 1993-12-01 核燃料公司 从耗尽核燃料再处理产生水溶液中分离某些元素的方法
CN1081530A (zh) * 1992-04-23 1994-02-02 核燃料公司 溶解钚和/或其它放射性元素的方法及其装置
US5422084A (en) * 1992-03-05 1995-06-06 Commissariat Energie Atomique Process for dissolving plutonium dioxide by means of OH- radicals produced by the radiolysis of water usable for the treatment of dissolving fines and plutoniferous waste
CN102776372A (zh) * 2012-08-21 2012-11-14 中国原子能科学研究院 铀、钚、镎共萃取的方法
CN103103369A (zh) * 2011-11-14 2013-05-15 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
CN103263849A (zh) * 2013-05-31 2013-08-28 西北核技术研究所 一种裂变产物中活化产物镓的快速分离方法
CN103420347A (zh) * 2012-05-17 2013-12-04 中国原子能科学研究院 一种硝酸蒸发回收过程中的除氟方法及装置
CN105110487A (zh) * 2015-09-06 2015-12-02 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
CN111863300A (zh) * 2020-06-10 2020-10-30 中国原子能科学研究院 一种purex流程污溶剂中保留钚的洗脱方法

Patent Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5154899A (en) * 1991-06-28 1992-10-13 Sturcken Edward F Metal recovery from porous materials
CN1078923A (zh) * 1992-03-03 1993-12-01 核燃料公司 从耗尽核燃料再处理产生水溶液中分离某些元素的方法
US5422084A (en) * 1992-03-05 1995-06-06 Commissariat Energie Atomique Process for dissolving plutonium dioxide by means of OH- radicals produced by the radiolysis of water usable for the treatment of dissolving fines and plutoniferous waste
CN1081530A (zh) * 1992-04-23 1994-02-02 核燃料公司 溶解钚和/或其它放射性元素的方法及其装置
CN103103369A (zh) * 2011-11-14 2013-05-15 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
CN103420347A (zh) * 2012-05-17 2013-12-04 中国原子能科学研究院 一种硝酸蒸发回收过程中的除氟方法及装置
CN102776372A (zh) * 2012-08-21 2012-11-14 中国原子能科学研究院 铀、钚、镎共萃取的方法
CN103263849A (zh) * 2013-05-31 2013-08-28 西北核技术研究所 一种裂变产物中活化产物镓的快速分离方法
CN105110487A (zh) * 2015-09-06 2015-12-02 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
CN111863300A (zh) * 2020-06-10 2020-10-30 中国原子能科学研究院 一种purex流程污溶剂中保留钚的洗脱方法

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
邓继勇等: "核废物的分离及处理技术研究进展", 《材料科学与工程》 *

Also Published As

Publication number Publication date
CN112593081B (zh) 2023-01-03

Similar Documents

Publication Publication Date Title
Inoue et al. Development of pyroprocessing and its future direction
Burns et al. Uranium: cradle to grave
CN108538417B (zh) 一种直接分离二氧化铀或者乏燃料中稀土元素的方法
CN112596093B (zh) 一种废树脂中钚的浸取方法
Peng et al. Magnetic fusion driven transmutation of nuclear waste (FTW)
CN112593081B (zh) 一种含钚活性炭中钚的浸取方法
Kim et al. A study on artificial rare earth (RE2O3) based neutron absorber
Setiawan et al. Preliminary analysis of high-flux rsg-gas to transmute am-241 of pwr’s spent fuel in asian region
JP2002243890A (ja) 使用済核燃料から全アクチノイドを分離・貯蔵・利用する方法
Chmielewski Chemistry for the nuclear energy of the future
Fetter et al. Is US reprocessing worth the risk?
Aruquipa et al. Reprocessing techniques of LWR spent fuel for reutilization in hybrid systems and IV generation reactors
CN210837205U (zh) 一种可回收富集硼酸的核电站工艺***
Pigford Thorium fuel cycles compared to uranium fuel cycles
Kubota Development of the partitioning process at JAERI
Baetsle A comparative systems-analysis approach on fuel cycles with partitioning and transmutation
Thompson et al. Solvent extraction of irradiated neptunium targets. I. Valence stabilization
Guoan Strategy Consideration and R&D Activities of Closed Nuclear Fuel Cycle in China
Culler Jr Nature of radioactive wastes
Lee et al. Advanced Fuel Cycle Initiative Comparison Report, FY 2005
Zerriffi et al. The Nuclear Alchemy Gamble
Ottensmeyer Nuclear fuel waste consumed and eliminated: environmentally responsible, economically sound, energetically enormous
Farrugia Reprocessing Radiated Fuel
Richards The US DOE strategy for permanent disposal of commercial LWR, spent nuclear fuel
Hall et al. Tritium control by water recycle in a nuclear fuel reprocessing plant

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant