Purex流程铀钚分离工艺单元数学模型研究
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摘要
在铀钚分离工艺单元单级数学模型和混合澄清槽瞬态数学模型的基础上,建立了以U(Ⅳ)-N_2H_4为还原反萃剂、混合澄清槽为萃取设备的Purex流程铀钚分离工艺单元数学模型,开发了计算机模拟程序,并使用台架实验数据对程序的可靠性进行了验证。结果表明,模拟程序的计算值和实验值符合良好。在此基础上,利用模拟软件对铀钚分离工艺单元的工艺参数进行了计算分析,结果表明:1BX_1加入位置、1BS和1BX_2酸度对钚反萃率无太大影响,但1BX_1加入位置和补萃级数对钚中去铀系数SF_(U/Pu)有一定影响。
A new model was proposed, and a computer program was developed to simulate the uranium/plutonium separation unit(1 B), based on the transient model and single-stage module on reductive stripping of plutonium with U(Ⅳ) from 30%TBP/OK. The reliability of the program was verified by the bench-test values. The results show that concentration profiles obtained from program are consistent with the experimental values. The program could predict the performance of the extraction contactor. The separation process was analyzed using the program, and the results show that 1 BX_1-stage location, nitric acid concentration in 1 BS and 1 BX_2 have no effect on plutonium back-extraction efficiencies, but 1 BX_1-stage location and various stages of supplement extraction have some effect on SF_(U/Pu).
A new model was proposed, and a computer program was developed to simulate the uranium/plutonium separation unit(1 B), based on the transient model and single-stage module on reductive stripping of plutonium with U(Ⅳ) from 30%TBP/OK. The reliability of the program was verified by the bench-test values. The results show that concentration profiles obtained from program are consistent with the experimental values. The program could predict the performance of the extraction contactor. The separation process was analyzed using the program, and the results show that 1 BX_1-stage location, nitric acid concentration in 1 BS and 1 BX_2 have no effect on plutonium back-extraction efficiencies, but 1 BX_1-stage location and various stages of supplement extraction have some effect on SF_(U/Pu).
引文
[1] 章泽甫,王俊峰,张天祥,等. 动力堆核燃料后处理工学[M]. 北京:原子能出版社,2013.
[2] SUZUKI A. Handbook on process and chemistry of nuclear fuel reprocessing, JAERI-Review 2001-038[R]. Japan: Japan Atomic Energy Research Institute, 2001.
[3] 任凤仪,周镇兴. 国外核燃料后处理[M]. 北京:原子能出版社,2006.
[4] TACHIMOLI S. EXTRA·M: A computing code system for analysis of the Purex process with mixer settler for reprocessing, JAERI-1331[R]. Japan: Japan Atomic Energy Research Institute, 1993.
[5] MITCHELL A D. SEPHIS-MOD4: A user’s manual to a revised model of the Purex solvent extraction system, ORNL-5471[R]. USA: Oak Ridge National Laboratory, 1979.
[6] WATSON S B, RAINEY R H. Modification of the SEPHIS computer code for calculating the Purex solvent extraction system, ORNL/TM-5123[R]. USA: Oak Ridge National Laboratory, 1975.
[7] KOZO G, KOICHIRO O, SHOJI F. Calculation code revised MIXSET for Purex process, PNCT 841-79-26[R]. Japan: Tokai Works Power Reactor and Nuclear Fuel Development Corporation, 1979.
[8] 何辉. N,N-二甲基羟胺在铀钚分离中的应用和计算机程序的开发[D]. 北京:中国原子能科学研究院,2001.
[9] 于婷,何辉,叶国安,等. U(Ⅳ)对Pu(Ⅳ)的单级还原反萃数学模型研究[J]. 核化学与放射化学,2017,39(6):413-421. YU Ting, HE Hui, YE Guoan, et al. Computer simulation of single-stage reductive stripping of U(Ⅳ) with Pu(Ⅳ)[J]. Journal of Nuclear and Radiochemistry, 2017, 39(6): 413-421(in Chinese).
[10] 朱兆武,何建玉,章泽甫,等. 稳态计算法分析Purex流程中U/Pu分离工艺铀酸分布[J]. 原子能科学技术,2003,37(5):422-427. ZHU Zhaowu, HE Jianyu, ZHANG Zefu, et al. Steady-state calculation and analysis for uranium and acid distribution profile in U/Pu separation stage of Purex process[J]. Atomic Energy Science and Technology, 2003, 37(5): 422-427(in Chinese).
[2] SUZUKI A. Handbook on process and chemistry of nuclear fuel reprocessing, JAERI-Review 2001-038[R]. Japan: Japan Atomic Energy Research Institute, 2001.
[3] 任凤仪,周镇兴. 国外核燃料后处理[M]. 北京:原子能出版社,2006.
[4] TACHIMOLI S. EXTRA·M: A computing code system for analysis of the Purex process with mixer settler for reprocessing, JAERI-1331[R]. Japan: Japan Atomic Energy Research Institute, 1993.
[5] MITCHELL A D. SEPHIS-MOD4: A user’s manual to a revised model of the Purex solvent extraction system, ORNL-5471[R]. USA: Oak Ridge National Laboratory, 1979.
[6] WATSON S B, RAINEY R H. Modification of the SEPHIS computer code for calculating the Purex solvent extraction system, ORNL/TM-5123[R]. USA: Oak Ridge National Laboratory, 1975.
[7] KOZO G, KOICHIRO O, SHOJI F. Calculation code revised MIXSET for Purex process, PNCT 841-79-26[R]. Japan: Tokai Works Power Reactor and Nuclear Fuel Development Corporation, 1979.
[8] 何辉. N,N-二甲基羟胺在铀钚分离中的应用和计算机程序的开发[D]. 北京:中国原子能科学研究院,2001.
[9] 于婷,何辉,叶国安,等. U(Ⅳ)对Pu(Ⅳ)的单级还原反萃数学模型研究[J]. 核化学与放射化学,2017,39(6):413-421. YU Ting, HE Hui, YE Guoan, et al. Computer simulation of single-stage reductive stripping of U(Ⅳ) with Pu(Ⅳ)[J]. Journal of Nuclear and Radiochemistry, 2017, 39(6): 413-421(in Chinese).
[10] 朱兆武,何建玉,章泽甫,等. 稳态计算法分析Purex流程中U/Pu分离工艺铀酸分布[J]. 原子能科学技术,2003,37(5):422-427. ZHU Zhaowu, HE Jianyu, ZHANG Zefu, et al. Steady-state calculation and analysis for uranium and acid distribution profile in U/Pu separation stage of Purex process[J]. Atomic Energy Science and Technology, 2003, 37(5): 422-427(in Chinese).