[1] |
(苏)BN捷姆利亚努仅. 核电站燃料后处理[M]. 第一版. 北京:原子能出版社,1996.
|
[2] |
Baron P, Boullis В, Germain M, et al. Extraction cycles design for La Hague plants[J]. Proceedings of Globa, 1993, 93: 12-17.
|
[3] |
Natarajan R.Reprocessing of FBTR mixed carbide fuel-some process chemistry aspects[C].Mumbai, India: Annual Conference of Indian Nuclear Society, 2005.
|
[4] |
He H, Lin M, Muroya Y, et al. Laser photolysis study on the reaction of nitrate radical with tributylphosphate and its analogues comparison with sulfate radical[J]. Phys Chem Chem Phys, 2004, 6: 1264-1268.
|
[5] |
Mincher B J, Mezyk S P,Martin L R. A pulse radiolysis investigation of the reactions of tributylphosphate with the radical products of aqueous nitric acid irradiation[J]. J Phys Chem, 2008, 112: 6275-6280.
|
[6] |
Tripathi S C, Ramanujam A, Gupta K K, et al. Studies on the identification of harmful radiolytic products of 30% TBP-n-dodecane-HNO3 by gas-liquid chromatography. Ⅱ. Formation and characterization of high molecular weight organophosphates[J]. Sep Sci Technol, 2001, 36: 2863-2883.
|
[7] |
Adamov V M, Andreev V I, Belyaev B N, et al. Radiolysis of an extraction system based on solutions of tri-n-butylphosphate in hydrocarbon diluents[J]. Sov Radiochem, 1988, 29: 775-781.
|
[8] |
Lasage D, Virelizier H, Jankowski C K, et al. Identification of minor products obtained during radiolysis of tributylphosphate(TBP)[J]. Spectroscopy,1997, 13: 275-290.
|
[9] |
Mincher B J, Elias G, Martin L R, et al. Radiation chemistry and the nuclear fuel cycle[J]. Journal of Radioanalytical and Nuclear Chemistry, 2009, 282(2): 645-649.
|
[10] |
Mincher B J, Mezyk S P. Radiation chemical effects on radiochemistry: a review of examples important to nuclear power[J]. Radiochimica Acta, 2009, 97(9): 519-534.
|
[11] |
周金鹏, 童天真, 林漳基. 强辐照场下Purex 过程溶剂的辐解研究Ⅰ. 30% TBP-煤油1mol/L HNO3 两相混合状态下TBP辐解生成DBP和MBP规律的研究[J]. 辐射研究与辐射工艺学报,1992,10(1):1-5.Zhou Jinpeng, Tong Tianzhen, Lin Zhangji. Study on the radiolysis of solvent used in Purex Process under the strong irradiation condition Ⅰ. study on the formation of DBP and MBP in the irradiated mixed state of 30%TBP-kerosene 1 mol/L HNO3[J]. Journal of Radiation Reasearch and Radiation Processing, 1992,1:000(in Chinese).
|
[12] |
Shevchenko V B, Smelov V S. The effect of mono-and dibutyl phosphates on the extraction of plutonium with tributyl phosphate[J]. The Soviet Journal of Atomic Energy, 1958, 5(5): 1455-1459.
|
[13] |
Stieglitz L, Becker R. Chemische und radiolytische solventzersetzung im PUREX-proze β[J]. Atomkernenergie Kerntechnik, 1985, 46(2): 76-80.
|
[14] |
Tripathi S C, Bindu P, Ramanujam A. Studies on the identification of harmful radiolytic products of 30% TBP-n-dodecane-HNO3 by gas-liquid chromatography. Ⅰ. Formation of diluent degradation products and their role in Pu retention behavior[J]. Sep Sci Technol,2001, 36:1463-1478.
|
[15] |
Pasquiou J Y,Livet J,Germain M, et al. Pu(Ⅳ) dibutylphosphate complexes in the purex process[C]. Dounreay, UK: Meeting on Solvent Extraction Techniques (EXTRACTION 87), 1987.
|
[16] |
Natarajan R. Reprocessing of FBTR mixed carbide fuel-some process chemistry aspects[C]. Mumbai, India: Annual Conference of Indian Nuclear Society, 2005.
|
[17] |
Kawaguchi Y, Morimoto K, Kitao T, et al. Study of solvent degradation in reprocessing MOX spent fuel: solvent degradation and its effect on Pu purification cycle[J]. Nippon Genshiryoku Gakkai Wabun Rombunshi, 2009, 8(3): 221-229.
|
[18] |
张清轩,罗隆俊,武德柱,等. Purex(2B)过程中硝酸羟氨还原Pu(Ⅳ)的研究[J]. 原子能科学技术,1982,5:12.Zhang Qingxuan, Luo Longjun, Wu Dezhu, et al. Study on reduction of Pu(Ⅳ) by hydroxylamine nitrate in Purex(2B) process[J]. Atomic Energy Science and Technology, 1982, 5: 12(in Chinese).
|
[19] |
于恩江,黄怀安. 硝酸羟胺在动力堆乏燃料后处理流程钚线第三循环中的应用[J]. 原子能科学技术,1993,27(5):451-457.Yu Enjiang, Huang Huaian. Application of hydroxylamine nitrate in the third cycle of plutonium line in spent fuel reprocessing process of power reactor[J]. 1993, 27(5): 451-457(in Chinese).
|
[20] |
Renard E V, Fedoseev D A, Milovanova A S, et al. Radiation chemical behavior of plutonium during the aging of its organic solutions[J]. Sov Radiochem, 1985, 27(3): 315-320.
|
[21] |
May I, Taylor R J, Wallwork A L, et al.The influence of dibutylphosphate on actinide extraction by 30% tributylphosphate[J]. Radiochimi Acta, 2000, 88(5): 283-290.
|
[22] |
Mincher B J, Modolo G, Mezyk S P. Review article: the effects of radiation chemistry on solvent extraction: 1. Conditions in acidic solution and a review of TBP radiolysis[J]. Solvent Extraction and Ion Exchange, 2009, 27(1): 1-25.
|
[23] |
Venkatesan K A, Robertselvan B, Antony M P, et al. Physiochemical and plutonium retention properties of hydrolytic and radiolytically degraded tri-n-amylphosphate[J]. Solvent Extraction and Ion Exchange, 2006, 24(5): 747-763.
|
[24] |
Maya L, Bopp C D. Extraction of zirconium from nitric acid media by butyl lauryl phosphoric acid in dodecane[J]. Journal of Inorganic and Nuclear Chemistry, 1978, 40(6): 1147-1151.
|
[25] |
IAEA. Status of Developments in the Back End of the Fast Reactor Fuel Cycle: IAEA Nuclear Energy Series[R]. Vienna: International Atomic Energy Agency, 2011.
|
[26] |
Eiben K H. 改进溶剂处理减少Purex工艺废物量[C]. 伦敦:乏燃料后处理会,1994.
|
[27] |
Velavendan P, Ganesh S, Pandey N K, et al. Gas chromatographic determination of di-n-butyl phosphate in radioactive lean organic solvent of FBTR carbide fuel reprocessing[C]. India: Proceedings of DAE-BRNS symposium on nuclear and radiochemistry, 2011.
|