ADUÓëU3O8ÈܽâÒºÝÍÈ¡ÐÔÄܶԱÈ

作者£º ºîÑåÁú£¬ÕÅöÎÒ°£¬ÂíÏþÎÄ£¬Îº ¸Õ ¡¾ 转载 ¡¿ À´Ô´£º »¯Ñ§¹¤³ÌÓë×°±¸ 2024-08-20

ºîÑåÁú£¬ÕÅöÎÒ°£¬ÂíÏþÎÄ£¬Îº  ¸Õ

£¨ÖкËËÄ0ËÄÓÐÏÞ¹«Ë¾µÚÒ»·Ö¹«Ë¾£¬¸ÊËà À¼ÖÝ 732850£©

 

Õª  Òª£ºÒÔ30%TBP-¼ÓÇâúÓÍΪÝÍÈ¡¼Á£¬¿¼²ìÁ˸ßŨ¶ÈÓ˵ÄÖØÓËËáï§(ADU)ÓëU3O8ÏõËáÈܽâÒºµÄÝÍȡЧ¹û¡£ÊµÑé½á¹û±íÃ÷£¬ADUÈܽâÒºµÄÝÍȡЧ¹ûÓÅÓÚU3O8ÈܽâÒº£¬2ÖÖÏõËáÈܽâÒºµÄÓËÊÕÂʾùËæÓËŨ¶ÈµÄÔö¼ÓÏÈÉý¸ßºó»ºÂýϽµ£¬ÓËŨ¶ÈΪ430 g/Lʱ£¬ÓËÊÕÂÊÈÔÓÐ95.43%ºÍ90.34%¡£ÆäÓËÊÕÂʾùËæÏà±ÈµÄÔö¼Ó¶øÔö¼Ó£¬ÔÚÏàͬÏà±ÈÏÂADUµÄÓËÊÕÂʽÏU3O8¸ßÔ¼5%¡£ÔÚËá¶ÈΪ0~2.5 mol/L£¬U3O8ÈܽâÒºÓËÊÕÂÊÔö·ù½ÏADU¿ì¡£7¼¶ÝÍÈ¡ºó£¬2ÖÖÈܽâÒº×îÖÕË®ÏàÖеÄÓËŨ¶È·Ö±ðΪ4.42 mg/LºÍ43.42 mg/L¡£2ÖÖÈܽâÒº½øÐе¥¼¶ÝÍÈ¡£¬È»ºó¶ÔÝÍȡҺ½øÐз´ÝÍ£¬·´ÝÍÒºÖÐÔÓÖʺ¬Á¿·ÖÎö½á¹û±íÃ÷£¬ADUÈܽâÒºµÄÔÓÖÊÈ¥³ýÂÊ£¾91%£¬¸ßÓÚU3O8ÈܽâÒºµÄÔÓÖÊÈ¥³ýÂÊ£¬×ÜÌå¶øÑÔADUµÄÝÍȡЧ¹û½ÏºÃ¡£

¹Ø¼ü´Ê£ºÏõËáÓËõ££»ÝÍÈ¡£»ÖØÓËËáï§£»U3O8      

 

×÷Õß¼ò½é£ººîÑåÁú£¨1989¡ª£©£¬ÄУ¬ÉÂÎ÷Î÷°²ÈË£¬¸ß¼¶¹¤³Ìʦ£¬Ë¶Ê¿£¬ºË»¯¹¤×¨Òµ

 

   Extraction performance of nitric solution of ADU and U3O8

 

Hou Yanlong, Wei Gang, Ma Xiaowen

£¨The First Filiale of 404 Company Limited, CNNC, Lanzhou 732850, China£©

 

Abstract: The extraction performance of the high concentration uranium solution, including the nitric solution of (NH4)2U2O7 and U3O8, was investigated by 30%TBP-kerosene as organic phase. The results show that the extraction effect of ADU nitric acid solution is better than that of U3O8 solution. The uranium yield of two nitric acid solutions increased first and then decreased slowly with the increase of uranium concentration. The recovery ratio of uranium is 95.43% ((NH4)2U2O7) and 90.34% (U3O8) under 430 g U/L. For the two solutions, the recovery ratio of uranium increases as the flow ratio increases. Moreover, the recovery ratio of (NH4)2U2O7 nitric solution is about 5% higher than that of U3O8 nitric solution. In the experimental acidity range of 0-2.5 mol/L, the uranium yield of two solutions increases with the increase of acidity. And the increase of U3O8 nitric solution is faster than that of (NH4)2U2O7 nitric solution. After 7th extraction, the uranium concentration of raffinate for (NH4)2U2O7 nitric solution and U3O8 nitric solution is 4.42 mg/L and 43.42 mg/L. Meanwhile, two nitric solutions were extracted by single-stage extraction and then stripped. The removal rate of ADU impurities is over 91% by analyzing the content of impurities in the stripping solution. The impurity removing efficiency of ADU is higher than U3O8 solution. The performance of ADU is better than U3O8.

Key words: uranyl nitrate; extraction; ammonium diuranate; triuranium octaoxide

 

Ŀǰ£¬ÓÉÓÚ¹úÄÚ¶ÔÄÜÔ´µÄÐèÇó²»¶ÏÔö¼Ó£¬ºËµç×÷ΪһÖÖÇå½à¸ßЧµÄÄÜÔ´¸ü¼ÓÒýÆðÁËÈËÃǵÄÖØÊÓ£¬Æä¹æÄ£Ò²ÔÚ²»¶ÏÀ©´ó[1-2]¡£ÔÚºËÄÜºÍÆ½ÀûÓÃÖУ¬Ë®Ò±ºóµÄÓË´¿»¯×÷ΪºËȼÁÏÑ­»·²»¿ÉȱÉٵŤÐò[3]£¬ÊÇÓË×ÊÔ´µÃÒÔÀûÓõÄÖØÒª»·½Ú[4]¡£

ÓË¿óʯÔÚˮұ³§¾­¹ýÑÐÄ¥¡¢½þÈ¡¡¢³ÁµíµÈһϵÁй¤ÒÕ£¬×îÖյõ½²úÆ·ÓË¿óŨËõÎï¡£µ«¸Ã²úÆ·Öк¬Óн϶àÔÓÖÊ£¬ÈçÁòËáÑΡ¢¹è¡¢¸Æ¡¢îâµÈÎïÖÊ£¬Ðë½øÒ»²½¾«ÖÆ£¬²ÅÄÜÂú×ãºóÐø²úÆ·µÄÒªÇó[5-6]¡£Ä¿Ç°£¬¹ú¼ÊÉÏ£¬ÓË´¿»¯×ª»¯µÄ·½·¨Ö÷ÒªÓÐʪ·¨ºÍ¸É·¨Á½ÖÖ[7]¡£Êª·¨¹¤ÒÕµÄÖ÷ÒªÌØÕ÷ÊÇͨ¹ýÈܽ⡢ÝÍÈ¡»òÀë×Ó½»»»µÈ·½Ê½À´È¥³ýÎïÁÏÖеÄÔÓÖÊ£¬Èç¼ÓÄôóCameco¡¢·¨¹úArevaµÈ¹«Ë¾¾ù²ÉÓô˷¨¡£¸É·¨¹¤ÒÕÔòÊÇÓÉÃÀ¹úÁªºÏ»¯Ñ§¹«Ë¾¿ª·¢µÄÒ»ÖÖÖÆ±¸·½·¨£¬Ö±½Ó¶ÔÔ­ÁϽøÐл¹Ô­·ú»¯£¬ÔÚÓËת»¯µÄ×îºó½×¶Î£¬Í¨¹ýUF6µÄ¾«ÁóÈ¥³ýÔÓÖÊ[8]¡£Ïà±È¸É·¨¹¤ÒÕ£¬Êª·¨¹¤ÒÕ¶ÔÎïÁÏÒªÇó½ÏµÍ£¬ÎïÁÏͨÐÔ¸ü´ó£¬Ê¹Ó÷¶Î§¸ü¹ã£¬ÊÇĿǰ¹ú¼ÊÉÏÓË´¿»¯×ª»¯µÄÖ÷Á÷¹¤ÒÕ·Ïߣ¬±»¹ã·ºÓ¦ÓÃÓÚÓ˵ÄÌá´¿[9-11]¡¢¸ß·Å·ÏÒº´¦Àí[12-13]µÈ¡£

ÖØÓËËáï§£¨ADU£©ºÍU3O8ÊÇÓË¿óŨËõÎïµÄÁ½ÖÖÖ÷ÒªÐÎʽ[14]¡£ADUÓëU3O8µÄÏõËáÈܽâÒº¾ßÓкÜÇ¿µÄÏàËÆÐÔ£¬ÆäÖ÷񻂿±ðÔÚÓÚADUÏõËáÈܽâÒºÖк¬ÓÐÏõËáï§£¬¶øU3O8ÏõËáÈܽâÒºÖв»º¬´ËÎïÖÊ¡£È»¶ø£¬Ä¿Ç°ÎÄÏ×ÖкÜÉÙÓÐÁ½ÕßµÄÝÍÈ¡¶Ô±ÈÑо¿¡£Òò´Ë£¬±¾ÎÄÄâ¶ÔADUºÍU3O8Á½ÖÖÏõËáÈܽâÒºÔÚÏàͬÝÍÈ¡Ìõ¼þϵÄÝÍÈ¡ÐÔÄܽøÐжԱȣ¬Ì½Ë÷ADUÈܽâÒººÍU3O8ÈܽâÒºÝÍÈ¡´¿»¯ÐÔÄܵÄÇø±ð£¬ÎªÆä¹¤ÒµÝÍÈ¡´¿»¯£¬ÓÈÆäÔÚͬһÉú²úÏß¹²ÓÃÉÏÌṩһ¶¨µÄÀíÂÛÖ§³Ö¡£ 

1  ÊµÑé

1.1  Ö÷ÒªÊÔ¼ÁÓëÒÇÆ÷

ADU¡¢U3O8¡¢TBP£¬·ÖÎö´¿£¬Ìì½òÊÔ¼ÁÒ»³§£»¼ÓÇâúÓÍ£¬½õÎ÷Á¶Óͳ§£»ÏõËᣬ68%£¬°×ÒøÁ¼ÓÑ»¯Ñ§ÊÔ¼ÁÓÐÏÞ¹«Ë¾£¬·ÖÎö´¿¡£

JJ-1ÐͽÁ°è»ú£¬³£Öݹú»ªµçÆøÓÐÏÞ¹«Ë¾£»CIT-3600ʯī¾§ÌåÔ¤ÑÜÉäXÉäÏßÓ«¹âÒÇ£¬ÉÂÎ÷ÎÀ·åºËµç×ÓÓÐÏÞ¹«Ë¾£»ICAP-6500È«Æ×Ö»¶ÁµÈÀë×ÓÌå¹âÆ×ÒÇ£¬ÃÀ¹úÈȵ繫˾¡£

1.2  ÏõËáÓËõ£ÈÜÒºÓëÝÍÈ¡¼ÁµÄÖÆ±¸

ÏõËáÓËõ£ÈÜÒºÖÆ±¸£ºÊ×ÏȽ«Ò»¶¨Á¿µÄ¹Ì̬ADUÓëU3O8·Ö±ðÓÃŨÏõËá½øÐÐÈܽ⣬ÅäÖÆ³É¸ßŨ¶ÈµÄÏõËáÓËõ£ÈÜÒº£¬È»ºóÓÃÏàÓ¦Ëá¶ÈµÄÏ¡ÏõËáÈÜÒºÔÚÈÝÁ¿Æ¿ÖнøÐж¨ÈÝ£¬ÅäÖÆ³É¶ÔÓ¦Ëá¶ÈºÍÓËŨ¶ÈµÄÏõËáÓËõ£ÈÜÒº¡£

ÝÍÈ¡¼ÁÖÆ±¸£º½«TBPÓë¼ÓÇâúÓͰ´ÕÕ30%µÄÌå»ý·ÖÊý½øÐÐÅä±È£¬ÆäÖÐTBPÕ¼30%¡£

1.3  ÊµÑé·½·¨

°´ÕÕµ¥¼¶ÝÍȡȡµÄ·½·¨½øÐÐÏõËáÓËõ£µÄÝÍÈ¡£¬¾ßÌå·½·¨ÈçÏ£ºÊ×ÏÈÁ¿È¡Ò»¶¨Á¿µÄ°´ÒªÇóÅäÖÆµÄÏõËáÓËõ£ÈÜÒºÓë30%TBP-¼ÓÇâúÓÍÒÀ´Î¼ÓÈëÉÕ±­ÖУ¬È»ºó½Á°è3 min£¬×îºó½«ÒºÌåµ¹Èë·ÖҺ©¶·Öо²Ö÷ֲ㣬ÆäÖÐÉϲãΪÝÍÈ¡ºóµÄº¬ÓËÓлúÏ࣬ϲãΪÝÍÈ¡ºóµÄÏõËáÓËõ£Ë®Ïà¡£¶ÔϲãË®Ïà½øÐÐÈ¡Ñù·ÖÎö£¬²â¶¨ÓËŨ¶È£¬²ÉÓÃÏÂʽ¼ÆËãADU»òU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊE£º

21.png                       (1)

ʽÖУºminΪÝÍȡǰÝÍÔ­ÒºÖÐÏõËáÓËõ£µÄÖÊÁ¿£¬g£»moutΪÝÍÈ¡ºóÝÍÓàÒºÖÐÏõËáÓËõ£µÄÖÊÁ¿£¬g¡£

ÝÍȡҺÖÐÓ˱¥ºÍ¶ÈSµÄ¼ÆË㹫ʽÈçÏ£º

22.png                                     (2)

ʽÖУºcoΪÝÍÈ¡ºóÝÍȡҺÖÐÏõËáÓËõ£µÄŨ¶È£¬g/L£»cosΪÝÍȡҺÏõËáÓËõ£µÄ×î´óÈܽâÁ¿£¬ÆäֵΪ130 g/L[15]¡£

1.4  ÈÜÒºÖÐÓËŨ¶È·ÖÎö·½·¨

¶ÔÓÚg¼¶ÏõËáÓËõ£µÄÈÜÒº£¬ÅäÖÆÖØ¸õËá¼Ø±ê×¼ÈÜÒº£¬Í¨¹ýÑõ»¯»¹Ô­µÄÔ­ÀíÀ´²â¶¨ÈÜÒºÖÐÏõËáÓËõ£µÄº¬Á¿£»¶ÔÓÚmg¼¶µÄÏõËáÓËõ£ÈÜÒº£¬Í¨¹ý¹âÆ×·ÖÎöÒǽøÐвâÁ¿¡£ 

2  ½á¹ûÓëÌÖÂÛ

2.1  ÓËŨ¶È¶ÔÓËÊÕÂʵÄÓ°Ïì

ÔÚÏõËáÓËõ£µÄÝÍÈ¡ÌåϵÖУ¬ÓËŨ¶È¶Ô×îÖÕµÄÓËÊÕÂÊÓÐÒ»¶¨µÄÓ°Ïì¡£ÔÚÊÒÎÂ24 ¡æ¡¢ADUºÍU3O8ÏõËáÈܽâÒºËá¶ÈΪ1.65 mol/L¡¢ÝÍÔ­ÒºÓëÝÍÈ¡¼ÁÏà±ÈΪ1:4.5µÄÌõ¼þÏ£¬¿¼²ì²»Í¬µÄÏõËáÓËõ£Å¨¶ÈÏÂADUºÍU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊ£¬½á¹ûÈçͼ1Ëùʾ¡£


23.png

ͼ1  ÈܽâÒºÖÐÓËŨ¶È¶ÔÓËÊÕÂʵÄÓ°Ïì

Fig.1  Effect of uranium concentration on yield of uranium


ÓÉͼ1¿ÉÖª£¬Ëæ×ÅÈܽâÒºÖÐÓËŨ¶ÈµÄÔö´ó£¬ADUºÍU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂʾù³ÊÏÈÔö¼Óºó»ºÂýϽµµÄÇ÷ÊÆ¡£Õâ¿ÉÄÜÊÇÓÉÓÚÓлúÏàÖÐÓ˺¬Á¿½Ï¸ßʱ£¬ÝÍÈ¡¼ÁËù½áºÏµÄÏõËáÓËõ£Ç÷ÓÚ±¥ºÍ£¬²»ÀûÓÚÓ˵ĽøÒ»²½ÝÍÈ¡£¬Òò¶øµ¼ÖÂÓËÊÕÂÊϽµ¡£´Ó¹¤ÒµÓ¦ÓõĽǶȳö·¢£¬Ìá¸ßÓ˵ÄŨ¶È£¬¿ÉÒÔÔö¼Ó²úÄÜ£¬Í¬Ê±¼õÉÙº¬ÓË·ÏË®£¬ÊµÏÖ½ÚÄܼõÅÅ£¬Òò¶øÈܽâÒºÖиßŨ¶ÈÓËËäʹÓËÊÕÂÊÓÐËùϽµ£¬µ«Ï½µ·ù¶È½ÏС£¬ÓËŨ¶ÈΪ430 g/Lʱ£¬ADUÓëU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊÈÔ·Ö±ð´ï95.43%Óë90.34%£¬Òò´ËÏà¶Ô¶øÑÔ£¬Ìá¸ßÈܽâÒºÖÐÓËŨ¶ÈÊÇÓÐÀûµÄ¡£

ͬʱ´Óͼ1»¹¿É¿´³ö£¬ÔÚÏàͬÌõ¼þÏ£¬ADUÏõËáÈܽâÒºµÄÓËÊÕÂʽÏU3O8ÏõËáÈܽâÒºµÄ¸ß£¬Ö÷ÒªÔ­ÒòÊÇADUÖк¬ÓÐ笠ùÀë×Ó£¬ÔÚÈܽâ¹ý³ÌÖÐÓëÏõËá·´Ó¦Éú³ÉNH4NO3£¬ÈÜÓÚÝÍÔ­ÒºÖУ¬ÆäÔÚÝÍÈ¡¹ý³ÌÖÐÆðµ½ÑÎÎö¼ÁµÄ×÷ÓÃ[16]£¬Òò¶øÊ¹µÃADUÈܽâÒºµÄÓËÊÕÂʽϸߡ£

2.2  Ëá¶È¶ÔÓËÊÕÂʵÄÓ°Ïì

Ëá¶ÈÊÇÓ°ÏìÏõËáÓËõ£ÈÜÒºÝÍÈ¡ÓËÊÕÂʵÄÒ»¸öÖØÒªÒòËØ¡£ÔÚADUºÍU3O8ÏõËáÈܽâÒºÖÐÓËŨ¶ÈΪ430 g/L¡¢ÝÍÈ¡¼ÁÓëÝÍÔ­ÒºÏà±ÈΪ4.5:1Ìõ¼þÏ£¬Ñо¿ÔÚ5ÖÖ²»Í¬Ëá¶ÈÏÂADUºÍU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊ£¬½á¹ûÈçͼ2Ëùʾ¡£


24.png

ͼ2  ÈܽâÒºËá¶È¶ÔÓËÊÕÂʵÄÓ°Ïì

Fig.2  Effect of acidity on yield of uranium

 

´Óͼ2¿ÉÖª£¬Ëæ×ÅËá¶ÈµÄÔö¼Ó£¬Á½ÖÖÈܽâÒºµÄÓËÊÕÂʾùËæÖ®Ìá¸ß£¬ÆäÖÐADUÏõËáÈܽâÒºµÄÌá¸ßËٶȽϻº£¬ÔÚʵÑéËá¶È·¶Î§ÄÚ£¬ÆäÓËÊÕÂÊÓÉ93.06%Éý¸ßÖÁ95.96%£¬¶øU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊÔöËÙ¸üΪÃ÷ÏÔ£¬´Ó×îµÍµÄ78.42%Ìá¸ßÖÁ92.11%£¬Õâ˵Ã÷Ëá¶È¶ÔU3O8ÈܽâÒºµÄÝÍȡЧ¹ûÓ°Ïì±È¶ÔADUÏõËáÈܽâÒº¸üΪÏÔÖø£¬¸üÒ×ÌáÉýÆäÝÍȡЧÂÊ£¬ÓÈÆäÊÇËá¶ÈµÍÓÚ1.0 mol/Lʱ£¬ÏõËáÌá¸ßÓËÊÕÂʵÄЧ¹û×îÏÔÖø¡£Õâ¿ÉÄÜÊÇÒòΪËá¶È½ÏµÍʱ£¬ÏõËáµÄÒýÈë¸üÓÐÀûÓÚ´Ù½øU3O8ÏõËáÈܽâÒºÝÍȡƽºâµÄÓÒÒÆ£¬ÓËÊÕÂÊÌá¸ß½Ï¿ì¡£Òò´Ë£¬ÔÚU3O8ÈܽâÒºµÄÝÍÈ¡¹ý³ÌÖÐËá¶È²»Ó¦Ð¡ÓÚ1.0 mol/L¡£

Ëá¶È¶ÔÌáÉýU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂʽÏADUÏõËáÈܽâÒº¸ßµÄÔ­ÒòÊÇÏõËáÔÚÝÍÈ¡¹ý³ÌÖÐÓëÏõËáï§×÷ÓÃÏàÀàËÆ£¬Ò²¾ßÓÐÑÎÎö×÷Óá£ÓÉÓÚU3O8ÏõËáÈܽâÒºÖÐûÓÐNH4NO3µÈÆäËûÑÎÎö¼ÁµÄ´æÔÚ£¬Òò¶øµ±ÏõËá×÷ΪÑÎÎö¼Á¼ÓÈëʱ¶ÔU3O8ÏõËáÈܽâÒºÓ°Ïì¸üÏÔÖø¡£ÕâҲͬʱ½âÊÍÁËADUÏõËáÈܽâÒº½ÏU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂʸߵÄÔ­Òò£¬ÒòΪADUÏõËáÈܽâÒºÖÐËùº¬ÓеÄÏõËáï§ÒÑÆðµ½ÁËÑÎÎöµÄ×÷Ó㬼ÓÈëÏõËáºó£¬¸ü´Ù½øÁËÝÍÈ¡¹ý³ÌÖеÄÑÎÎöЧӦ£¬Òò´ËADUÏõËáÈܽâÒº½ÏU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂʸߡ£

2.3  Ïà±È¶ÔÓËÊÕÂʵÄÓ°Ïì

ÔÚADUºÍU3O8ÏõËáÈܽâÒºÓËŨ¶ÈΪ430 g/L¡¢Ëá¶ÈΪ1.65 mol/LÌõ¼þÏ£¬Ñо¿ÝÍÈ¡¼ÁÓëÝÍÔ­ÒºµÄÏà±È¶ÔÓËÊÕÂʵÄÓ°Ï죬½á¹ûÁÐÓÚ±í1¡£Óɱí1¿ÉÖª£¬ÈܽâÒºµÄÓËÊÕÂÊËæÏà±ÈµÄÔö¼Ó¶øÔö¼Ó£¬Ïà±ÈΪ4.0ʱ£¬ADUÏõËáÈܽâÒºµÄÓËÊÕÂÊ´ï93.21%¡£¶øÓËÊÕÂʵÄÔö·ùËæ×ÅÏà±ÈµÄÔö¼Ó£¬ÆäÔö¼ÓÇ÷ÊÆÖ𽥱仺¡£Õâ˵Ã÷ÓËÊÕÂʲ¢²»ÊÇËæÏà±ÈµÄÔö´ó¶øÎÞÏÞÔö¼ÓµÄ¡£´Ó±í1Ò²¿É¿´³ö£¬ÔÚÏàͬµÄÏà±ÈÏ£¬ADUÏõËáÈܽâÒºµÄÝÍȡЧ¹ûºÃÓÚU3O8ÏõËáÈܽâÒº¡£


±í1  Ïà±È¶ÔÓËÊÕÂʵÄÓ°Ïì

Table 1  Effect of flow ratio on yield of uranium

Ïà±È

ÓËÊÕÂÊ

ADUÈܽâÒº

U3O8ÈܽâÒº

3.0

80.44

75.69

3.5

88.46

84.86

4.0

93.21

88.13

4.5

95.43

90.34

 

²»Í¬Ïà±ÈÏ£¬Á½ÖÖÈܽâÒºµÄÝÍÈ¡¼ÁÖÐÓ˵ı¥ºÍ¶ÈÁÐÓÚ±í2¡£Óɱí2¿É¿´³ö£¬Ïà±ÈÔ½µÍ£¬ÆäÏàÓ¦µÄÓ˱¥ºÍ¶ÈÔ½¸ß£¬Ïà±ÈΪ3.0ʱ£¬Ó˵ı¥ºÍ¶ÈΪ88.06%¡£µ«±¥ºÍ¶ÈµÄÌá¸ß£¬È´²»ÀûÓÚÓËÊÕÂʵÄÌá¸ß£¬Á½ÕßÖ®¼ä³Ê·´Ïò¹ØÏµ£¬ÕâÊÇÒòΪÝÍȡҺÖÐÓ˺¬Á¿µÄÔö¼Ó£¬×è°­ÁËÝÍȡƽºâµÄ½øÒ»²½ÓÒÒÆ£¬´Ó¶ø½µµÍÁËÓËÊÕÂÊ¡£ÕâÒ²½âÊÍÁËËæ×ÅÏà±ÈµÄÔö¼Ó£¬ÝÍȡƽºâ»á½øÒ»²½ÓÒÒÆ£¬Òò¶øÓËÊÕÂÊÔö¼Ó£¬µ«ÝÍÈ¡×îÖÕ»á´ïµ½Æ½ºâ£¬Òò´ËÓËÊÕÂʵÄÔö·ù±ä»º£¬×îÖÕÇ÷ÓÚÒ»¸ö²»±äµÄ¶¨Öµ¡£

Òò´ËÔÚ½øÐÐ¶à¼¶ÄæÁ÷ÝÍÈ¡µÄ¹ý³ÌÖУ¬ÎªÌáÉýÝÍȡЧÂÊ£¬Ïà±È²»Ó¦Ì«Ð¡£¬·ñÔò»áµ¼ÖÂÓ˱¥ºÍ¶È¹ý¸ß£¬´Ó¶ø½µµÍÓËÊÕÂÊ£»µ«Ïà±ÈÒ²²»Ó¦¹ý¸ß£¬·ñÔò»áµ¼ÖÂÝÍÈ¡¼ÁµÄÀûÓÃÂʽµµÍ¡£

 

±í2  ²»Í¬Ïà±ÈÏÂÝÍȡҺµÄ¼°Ó˱¥ºÍ¶È

Table 2  Uranium concentration and saturation of extraction in different flow ratios

Ïà±È

±¥ºÍ¶È/%

ADUÏõËáÈܽâÒº

U3O8ÏõËáÈܽâÒº




3.0

88.06

83.42

3.5

83.55

80.16

4.0

77.05

72.85

4.5

70.11

66.37

 

2.4  ÝÍÈ¡¼¶Êý¶ÔÓËÊÕÂʵÄÓ°Ïì

ΪÑо¿ÝÍÈ¡¼¶Êý¶ÔÁ½ÖÖÎïÁÏÏõËáÈܽâÒºÓËÊÕÂʵÄÓ°Ï죬ѡÓÃÐÂÏÊÝÍÈ¡¼Á¶ÔÓËŨ¶ÈΪ420 g/L¡¢Ëá¶ÈΪ1.65 mol/LµÄADUºÍU3O8ÏõËáÈܽâÒº·Ö±ð½øÐж༶´íÁ÷ÝÍÈ¡£¬²âÁ¿·ÖÎöÿ¼¶ÝÍÈ¡ºóµÄË®ÏàÓËŨ¶È£¬²¢¸ù¾Ý¸ÃÓËŨ¶È¼ÆËãÓËÊÕÂÊ£¬ÁÐÓÚ±í3¡£

´Ó±í3¿É¿´³ö£¬ADUÏõËáÈܽâÒºµÄÝÍȡЧÂʸßÓÚU3O8ÏõËáÈܽâÒº£¬ÔÚÆäÍê³ÉÈý¼¶ÝÍȡʱ£¬ÓËÊÕÂÊÒѳ¬¹ýÁËU3O8ÏõËáÈܽâÒºµÄ7¼¶ÝÍÈ¡ÓËÊÕÂÊ¡£ÔÚÝÍÈ¡7´Îºó£¬Á½ÖÖÈܽâÒºµÄÓËÊÕÂʶ¼½Ï¸ß£¬·Ö±ðΪ99.998%ºÍ99.990%¡£µ«Ðë×¢ÒâµÄÊÇÔÚADUÏõËáÈܽâÒº½øÐеÚ5¼¶ÝÍȡʱ£¬Ë®ÏàÈÜÒºÖпªÊ¼³öÏÖ΢Á¿È黯£¬µÚ7¼¶ÝÍȡʱ£¬Ë®ÏàÖÐÓн϶àÈ黯Îµ«È黯Îï½ÏΪ¾ùÒ»£¬ÕâÓпÉÄÜÊÇÔÚËá¶È½ÏµÍµÄÇé¿öÏ£¬ÏõËáÓËõ£ÓëÈÜÒºÖеÄ笠ùÀë×ÓÐγÉÁËÂçºÏÎï¶øµ¼Öµġ£ÎªÊ¹ÓËŨ¶È·ÖÎö¸üΪ׼ȷ£¬Ã¿¼¶ÓËŨ¶È¾ù²ÉÓÃʯī¾§ÌåÔ¤ÑÜÉäXÉäÏßÓ«¹âÒǽøÐзÖÎö£¬¸Ã·½·¨±ê׼ƫ²îΪ5%¡£ÓëÖ®Ïà¶Ô±È£¬U3O8ÏõËáÈܽâÒºÔÚ7¼¶ÝÍÈ¡¹ý³ÌÖÐδ³öÏÖÈ黯ÏÖÏó¡£

 

±í3  ¶à¼¶ÝÍÈ¡ÏÂÝÍÔ­ÒºµÄÓËŨ¶ÈºÍÓËÊÕÂÊ

Table 3  Yield of uranium under multistage extraction for original extraction solution

ÝÍÈ¡¼¶Êý

ADUÏõËáÈܽâÒº

U3O8ÏõËáÈܽâÒº

ÓËŨ¶È/£¨mg¡¤L-1£©

ÓËÊÕÂÊ/%

ÓËŨ¶È/£¨mg¡¤L-1£©

ÓËÊÕÂÊ/%

1

22.70¡Á103

94.595

40.00¡Á103

90.476

2

338.74

99.919

2.71¡Á103

99.355

3

16.80

99.996

458.00

99.891

4

10.13

99.997

152.47

99.964

5

9.67

99.997

94.26

99.777

6

5.24

99.998

44.54

99.894

7

4.42

99.998

43.42

99.990

 

2.5  ÝÍÈ¡¶ÔÈÜÒºÖÐÔÓÖʾ»»¯µÄÓ°Ïì

Ñ¡ÓÃÓËŨ¶ÈΪ420 g/L¡¢Ëá¶ÈΪ1.65 mol/LµÄADUºÍU3O8ÏõËáÈܽâÒº×÷ΪÝÍÔ­Òº£¬¶ÔÝÍÔ­Òº½øÐе¥¼¶ÝÍÈ¡£¬È»ºó¶ÔÝÍÈ¡ºóµÄÓлúÏà½øÐе¥¼¶·´ÝÍ£¬½«ÏõËáÓËõ£ÖØÐÂÝͻص½Ë®ÏàÖУ¬Í¨¹ý¹âÆ×ÒÇ·ÖÎöË®ÏàÈÜÒºÖеÄÔÓÖÊÔªËØ£¬ÆäÖÐ15ÖÖº¬Á¿½Ï¸ßµÄÔÓÖÊÔªËØµÄ·ÖÎö½á¹ûÁÐÓÚ±í4¡£Óɱí4¿ÉÖª£¬ÆäÖÐCr¡¢Cu¡¢Fe¡¢Mn¡¢Mo¡¢Na¡¢Ni¡¢Ti¡¢V¡¢WºÍAsµÈ10ÖÖÔÓÖÊÔªËØÔÚADUÏõËáÈܽâÒºÖеĺ¬Á¿µÍÓÚU3O8ÏõËáÈܽâÒºÖе쬯äËû5ÖÖÔÓÖÊÔªËØº¬Á¿¸ßÓÚU3O8ÏõËáÈܽâÒºÖеġ£´Ó±í4»¹¿É¿´³ö£¬ADU·´ÝÍÒºÖеÄÔÓÖÊÔªËØº¬Á¿ÆÕ±éµÍÓÚU3O8·´ÝÍÒºÖеģ¬ADUÏõËáÈܽâÒºµÄÔÓÖÊÈ¥³ýÂʸßÓÚU3O8ÏõËáÈܽâÒº¡£²¢ÇÒ£¬ADUÏõËáÈܽâÒºÖгýCrºÍMnÍ⣬ÆäËûÔÓÖÊͨ¹ýµ¥¼¶ÝÍÈ¡·´ÝÍÈ¥³ýÂÊ»ù±¾ÔÚ91%ÒÔÉÏ£¬¶øW¡¢CrºÍMnÓÉÓÚÔÚÈÜÒºÖеĺ¬Á¿µÍÓÚ¹âÆ×ÒÇÆ÷µÄ²âÁ¿ÏÂÏÞ£¬Òò´ËÎÞ·¨×¼È·¼ÆËã³öÆäÈ¥³ýÂÊ£¬Í¨¹ýÓËת»¯¹ý³ÌÖмä²úÆ·µÄÖÊÁ¿¿ØÖÆÖ¸±ê¶Ô±È[17]¿ÉÖª£¬ÕâÁ½ÖÖÔÓÖÊÔªËØµÄº¬Á¿·ûºÏÖÊÁ¿ÒªÇó¡£×ÜÌåÉÏ£¬ADUÏõËáÈܽâÒºµÄÔÓÖÊÈ¥³ýЧ¹ûºÃÓÚU3O8ÏõËáÈܽâÒº¡£

 

±í4  ÈÜÒºÖÐÔÓÖÊÔªËØµÄº¬Á¿

Table 4  Content of impurity element in solution

ÔÓÖÊ

ÔªËØ

ADUÏõËáÈܽâÒº

U3O8ÏõËáÈܽâÒº

ÝÍÔ­Òº

ÔÓÖʺ¬Á¿

/(¦Ìg¡¤g-1£¨U£©)

·´ÝÍÒº

ÔÓÖʺ¬Á¿

/(¦Ìg¡¤g-1£¨U£©)

³ýÔÓЧÂÊ/%

ÝÍÔ­Òº

ÔÓÖʺ¬Á¿

/(¦Ìg¡¤g-1£¨U£©)

·´ÝÍÒº

ÔÓÖʺ¬Á¿

/(¦Ìg¡¤g-1£¨U£©)

ÔÓÖÊÈ¥³ýÂÊ/%

Al

471.5

17.2

96.35

199.5

20.9

89.52

Ca

880.1

8.1

99.08

205.1

82.7

59.68

Cr

3.9

<2.5

>35.90

9.9

<2.5

>74.75

Cu

1.0

<0.5

>50.00

4.5

0.6

>86.67

Fe

1162

40.7

96.50

2289

91.3

96.01

K

21.3

0.8

96.24

20.2

4.7

76.73

Mg

94.9

3.8

96.00

68.2

8.8

87.10

Mn

2.8

<0.5

>82.14

3.3

<0.5

>84.85

Mo

69.6

<0.5

>99.28

93.5

2.6

97.22

Na

133.6

5.7

95.73

192.3

19.5

89.86

Ni

1.0

<0.5

>50.00

8.6

<0.5

>94.19

Sr

24.9

0.8

96.79

43.6

1.4

96.79

Ti

6.0

<0.5

>91.67

8.2

0.6

92.68

V

11.9

<0.2

>98.32

14.0

<0.2

>98.57

W

2.1

<0.5

>76.19

2.6

<0.5

>80.77

As

17.7

<0.5

>97.17

21.3

1.4

93.43

 

2.6  ÏõËáï§¶ÔÈܽâÒºÝÍÈ¡ÓËÊÕÂʵÄÓ°Ïì

ADUÏõËáÈܽâÒºÓëU3O8ÏõËáÈܽâÒºÖ÷񻂿±ðÔÚÓÚADUÔÚÏõËáÈܽâµÄ¹ý³ÌÖлᷴӦÉú³ÉÏõËáï§£¬ÎªÌ½¾¿ÏõËáï§¶ÔÝÍÈ¡µÄÓ°Ï죬ÔÚÏàͬÏà±ÈÏ£¬ÔÚËá¶ÈΪ0.28 mol/L¡¢1.00 mol/L¡¢1.68mol/LµÄ3ÖÖU3O8ÏõËáÈܽâÒºÖзֱð¼ÓÈ벻ͬŨ¶ÈµÄÏõËáï§£¬¶ÔÆä½øÐе¥¼¶ÝÍÈ¡£¬ÆäÓËÊÕÂÊÁÐÓÚ±í5¡£


±í5  ²»Í¬ÏõËá狀¬Á¿ÏÂU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊ

Table 5  Yield of uranium of Nitric Solution of U3O8 with different concentrations of NH4NO3

NH4NO3º¬Á¿/(g¡¤L-1)


ÓËÊÕÂÊ/%


Ëá¶È0.28mol¡¤L-1

Ëá¶È1.00mol¡¤L-1

Ëá¶È1.68mol¡¤L-1

0

78.42

89.52

90.34

36

83.76

91.35

92.51

72

88.35

92.81

93.98

108

90.28

93.22

95.02

144

93.06

94.94

95.43

 

 

´Ó±í5¿É¿´³ö£¬ÔÚ3ÖÖËá¶ÈÏ£¬U3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊËæÏõËá狀¬Á¿µÄÔö¼Ó¶øÔö´ó£¬ÇÒÔö´ó·ù¶È½ÏΪÃ÷ÏÔ£¬Õâ˵Ã÷NH4NO3Ũ¶ÈµÍÓÚ144 g/Lʱ£¬ÆäÔÚÏõËáÓËõ£µÄÝÍÈ¡¹ý³ÌÖÐÆðÖúÝÍ×÷Óã¬ÓÐÀûÓÚÌá¸ßÏõËáÓËõ£µÄÝÍȡЧÂÊ¡£ÕâÊÇÓÉͬÀë×ÓЧӦÒýÆðµÄ£¬ÔÚÈÜÒºÖÐNH4NO3µç½â·ÖÀë³öÏõËá¸ùÀë×ÓÒÖÖÆÁËÏõËáÓËõ£µÄ·Ö½â£¬´Ó¶øÌá¸ßÁËÏõËáÓËõ£µÄÓËÊÕÂÊ¡£

3  ½áÂÛ

1£© ÔÚÏàͬÌõ¼þÏ£¬ADUÏõËáÈܽâÒºµÄÓËÊÕÂʸßÓÚU3O8ÏõËáÈܽâÒº£¬ÝÍȡЧÂʽϸߡ£

2£© ADUÓëU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊËæÏõËáÓËõ£Å¨¶ÈµÄÔö¼Ó³ÊÏÈÔö¼Óºó¼õСµÄÇ÷ÊÆ£¬¿ªÊ¼Ê±Ôö·ù½Ï¿ì£¬´ïµ½·åÖµºó¿ªÊ¼Ï½µ£¬µ«½µ·ù½Ï»ºÂý¡£

3£© ADUÓëU3O8ÏõËáÈܽâÒºµÄÓËÊÕÂÊÔÚÒ»¶¨·¶Î§ÄÚËæÏà±ÈºÍËá¶ÈµÄÔö¼Ó¶øÔö¼Ó¡£

4£© ADUÓëU3O8ÏõËáÈܽâÒº¾­7¼¶ÝÍÈ¡ºó£¬×îÖÕË®ÏàÖÐÓËŨ¶È·Ö±ðΪ4.42 mg/LºÍ43.42 mg/L£¬ÓËÊÕÂÊ·Ö±ð´ï99.998%Óë99.990%¡£

5£© ADUÏõËáÈܽâÒºµ¥¼¶ÝÍÈ¡·´Ý͵ÄÔÓÖÊÈ¥³ýÂʸßÓÚU3O8ÏõËáÈܽâÒº£¬ÆäÔÓÖÊÈ¥³ýÂÊ»ù±¾ÔÚ91%ÒÔÉÏ¡£

6£© µ±NH4NO3Ũ¶ÈµÍÓÚ144g/LÏÂʱ£¬NH4NO3ÔÚÏõËáÓËõ£µÄÝÍÈ¡ÖÐÆðÖúÝÍ×÷Óá£

 

²Î¿¼ÎÄÏ×£º

[1]  ÎéºÆËÉ,Òë. WNA¹«²¼ÊÀ½çºËȼÁÏÊг¡Î´À´¹©ÐèÕ¹Íû±¨¸æ[J]. ±±¾©:¹úÍâºËÐÂÎÅ,2007(10):22-22.

[2]  ÑîÐË´æ,°ü²®ÈÙ,ÖÜ·¼,µÈ. ÈܼÁÝÍÈ¡·¨ÔÚ·¦È¼ÁϺó´¦ÀíÖеÄÓ¦ÓÃÓëÑо¿¸ÅÊö[J]. Ô­×ÓÄÜ¿ÆÑ§¼¼Êõ,2001,35(5):50-55.

Yang Xingchun, Bao Borong, Zhou Fang, et al. The application and research overview of solvent extraction in spent fuel after treatment[J]. Atomic Energy Science and Technology, 2001, 35(5): 50-55(in Chinese).

[3]  ÍõµÂÒå,ÚȾ¹Çå,ÕÔÊçÁ¼. Ó˵ÄÌáÈ¡Óë¾«ÖÆ¹¤ÒÕѧ[M]. ±±¾©:Ô­×ÓÄܳö°æÉçm1982:246-258.

[4]  Å£ÓñÇ壬ÕÔ·ï᪣¬Êæ×æ¿¥£¬µÈ. ÓÃTBPÈܽâÝÍÈ¡·¨ÖƱ¸ºËµç´¿¶þÑõ»¯ÓË[J]. ºË»¯Ñ§Óë·ÅÉ仯ѧ,2011,33(3)£º136-147.

Niu Yuqing, Zhao Fengqi, Shu Zujun, et al. Preparation of nuclear power grade UO2 by TBP solvent extraction technology[J]. Journal of Nuclear and Radiochemistry, 2011, 33(3): 136-147(in Chinese).

[5]  µË×ôÇä,»ÆÂ×¹â,ׯº£ÐË,µÈ. ÎÒ¹úÌìÈ»ÓË´¿»¯¼¼ÊõÑо¿µÄ·¢Õ¹ÓëÏÖ×´[J]. ÓË¿óÒ±,1998,17(4):231-238.

Deng Zuoqing, Huang Lunguang, Zhuang Haixing, et al. The development and current status of natural uranium purification technology in China[J]. Uranium Mining and Metallurg, 1998, 17(4): 231-238(in Chinese).

[6]  ¹¨µÀÀ¤,ÍõÓ¢. ÌìÈ»ÓË´¿»¯ÝÍÓàÈÜÒºµÄÑ­»·ÀûÓÃÑо¿[J]. ÓË¿óÒ±,2018,37(2):108-111.

Gong Daokun, Wang Ying. Study on the recycling of extraction raffinate in the natural uranium purification[J]. Uranium Mining and Metallurg, 2018, 37(2): 108-111(in Chinese).

[7]  ÈηïÒÇ,ÖÜÕòÐË. ¹úÍâºËȼÁϺó´¦Àí[M]. ±±¾©:Ô­×ÓÄܳö°æÉç,2004:65.

[8]  Horng J. Semi-Empirical model for liquid-liquid extraction of UO2(NO3)2¨CTBP-kerosene system in acid medium[J]. Ind Eng Chem Process Res Dev, 1984, 23(3): 603-609.

[9]  ÑîÑåÐÂ,½ðç²Õä,ÕÅÈØ·¼. ÓÃ5208ÝÍÈ¡¼Á´ÓÏõËáÈÜÒºÖÐÝÍÈ¡ÓË[J]. ÓË¿óÒ±,1991,10(3): 31-38.

Yang Yanxin, Jin Qizhen, Zhang Rongfang. The extraction of uranium from nitric acid with 5208 extractants[J]. Uranium Mining and Metallurg, 1991, 10(3): 31-38(in Chinese).

[10] ÀîºêÓî,ÉêÀûºì,ÕÅÀÖ,µÈ. ßäàµÐ͹¦ÄÜÀë×ÓÒºÌåºÏ³É¼°¶ÔÓË£¨¢ö£©µÄÝÍÈ¡[J]. Ô­×ÓÄÜ¿ÆÑ§¼¼Êõ£¬2014£¬48(3):390-394.

Li Hongyu, Shen Lihong£¬Zhang Le, et al. Synthesis of imidazole-type TSIL and extraction for uranium(¢ö)[J]. Atomic Energy Science and Technology, 2014, 48(3): 390-394(in Chinese).

[11] GIRIDHAR P, VENKATESAN K A, SRINIVASAN T G. Extraction of uranium(¢ö) from nitric acid medium by 1.1 M tri-n-butylphosphate in ionic diluent[J]. Journal of Radioanalytical and Nuclear Chemistry, 2005(1):265£¨1£©£º31-38.

[12] ¸ß½Ü,Ò¶¸Ö,³ÂáÂÕÜ,µÈ. ¸ß·Å·ÏÒº³ýïȼ¼ÊõµÄÑо¿½øÕ¹[J]. Ô­×ÓÄÜ¿ÆÑ§¼¼Êõ,2013,47(6):99-102.

Gao Jie, Ye Gang, Chen Songzhe, et al. Development of partitioning of Sr from high level liquid waste[J]. Atomic Energy Science and Technology, 2013, 47(6): 99-102(in Chinese).

[13] ½¹ÈÙÖÞ,ËγçÁ¢,ÖìÓÀî£. ÝÍÈ¡·ÖÀë·¨´¦Àí¸ß·Å·ÏÒºµÄ½øÕ¹[J]. Ô­×ÓÄÜ¿ÆÑ§¼¼Êõ,2000,34(5):111-115.

Jiao Rongzhou, Song Chongli, Zhu Yongrui. The progress in the treatment of high level waste liquid by extration[J]. Atomic Energy Science and Technology, 2000, 34(5): 111-115(in Chinese).

[14] ÕÔÊÀÖÒ. Ó˽ðÊô¹¤ÒÕѧ[M]. ±±¾©:ÖйúºË¹¤Òµ×ܹ«Ë¾ËÄ©–Ëij§±¨ÉçÓ¡Ë¢³§,1993.

[15] ½ªÊ¥½×,ÈηïÒÇ ºËȼÁϺó´¦Àí¹¤Ñ§[M]. ±±¾©:Ô­×ÓÄܳö°æÉç,1995.

[16] Íõ×ÔÇ¿,ÈηïÒÇ,ÑÖÐÄÖÇ. ºËȼÁϺó´¦Àí[M]. ±±¾©: ÖйúºË¹¤Òµ×ܹ«Ë¾ËÄ©–Ëij§±¨ÉçÓ¡Ë¢³§,1994.

[17] ÀõÍòÈÊ,κ¸Õ,Ò¦ÊØÖÒ. ÓËת»¯¹¤ÒÕѧ[M]. ±±¾©:ÖйúÔ­×ÓÄܳö°æÉç,2012.


0评论

推荐

  • QQ空间

  • 新浪微博

  • 人人网

  • 豆瓣

È¡Ïû
技术支持£º ʱ´úÖ®¹â