核化学与放射化学
覈化學與放射化學
핵화학여방사화학
HE HUAXUE YU FANGSHE HUAXUE
2014年
3期
181-185
,共5页
董晓雨%郑小北%宋昱龙%刘玉侠%张岚
董曉雨%鄭小北%宋昱龍%劉玉俠%張嵐
동효우%정소북%송욱룡%류옥협%장람
钍基熔盐堆%四氟化铀%四氟化钍%高温水解%溶解
釷基鎔鹽堆%四氟化鈾%四氟化釷%高溫水解%溶解
토기용염퇴%사불화유%사불화토%고온수해%용해
thorium molten salt reactor%uranium tetrafluoride%thorium tetrafluoride%pyro-hydrolysis%dissolution
为适应钍基熔盐堆核燃料水法后处理的需求,需将乏燃料中难溶的氟化物转化为相应的氧化物形式,因此提出了高温水解的方法来实现这一目的。研究了 UF4、ThF4在不同反应温度和反应时间下的高温水解行为,对其水解产物进行了结构表征和溶解实验的研究。结果表明,UF4、ThF4分别在300℃和350℃即可全部转化为相应的氧化物 UO2.25和 ThO2。溶解实验结果表明,二者的高温水解产物较易溶解在3 mol/L HNO3和Thorex试剂中。
為適應釷基鎔鹽堆覈燃料水法後處理的需求,需將乏燃料中難溶的氟化物轉化為相應的氧化物形式,因此提齣瞭高溫水解的方法來實現這一目的。研究瞭 UF4、ThF4在不同反應溫度和反應時間下的高溫水解行為,對其水解產物進行瞭結構錶徵和溶解實驗的研究。結果錶明,UF4、ThF4分彆在300℃和350℃即可全部轉化為相應的氧化物 UO2.25和 ThO2。溶解實驗結果錶明,二者的高溫水解產物較易溶解在3 mol/L HNO3和Thorex試劑中。
위괄응토기용염퇴핵연료수법후처리적수구,수장핍연료중난용적불화물전화위상응적양화물형식,인차제출료고온수해적방법래실현저일목적。연구료 UF4、ThF4재불동반응온도화반응시간하적고온수해행위,대기수해산물진행료결구표정화용해실험적연구。결과표명,UF4、ThF4분별재300℃화350℃즉가전부전화위상응적양화물 UO2.25화 ThO2。용해실험결과표명,이자적고온수해산물교역용해재3 mol/L HNO3화Thorex시제중。
To meet the needs of the aqueous-reprocessing of used fuel from thorium molten salt reactor,the insoluble fluorides need to be converted into their corresponding oxides form.To realize this,a pyrohydrolysis method was proposed.The pyrohydrolysis behavior of UF4 and ThF4 under different temperature and time was studied,and the structural characterization of the pyrohydrolysis products and the dissolution tests of the products were performed.The results show that,UF4 and ThF4 are entirely converted into their corre-sponding oxides UO2.25 and ThO2 at 300 ℃ and 350 ℃.The results of the dissolution tests show that the pyrohydrolysis products of both UF4 and ThF4 can easily dissolved in 3 mol/L HNO3 and Thorex solution,respectively.
