Aqueous reprocessing

Christiansen, B., Apostolidis, C., Carlos, R. et al. 2004. Advanced aqueous reprocessing in P T strategies Process demonstrations on genuine fuels and targets. Radiochim. Acta 92 (8) 475-480. 

Takata, T., Koma, Y., Sato, K. et al. 2004. Conceptual design study on advanced aqueous reprocessing system for fast reactor fuel cycle. J. Nucl. Sci. Technol. 41 (3) 307-314. 

Richards, R. B. 1957. Aqueous reprocessing—an introduction. In Symposium on the Reprocessing of Irradiated Fuels, Book 1. U.S. Atomic Energy Commission Report No. TID-7534, Belgium, 3-21. 

Keder, W. E., Wilson, A. S., Burger, L. L., Symp. Aqueous Reprocessing Irradiated Fuels, Rrussels, European Nucl. Energy Agency (1963). 

Aqueous reprocessing methods have been developed to effect an efficient and thorough separation of fissile elements from the contaminating fission products in spent fuel( l). While these processes may be altered to yield a proliferations-resistant product by coprocessing or by the addition of radioactive material that will contaminate the clean fissile material, it still is necessary to safeguard some of the process steps to ensure that material useful in nuclear weapons will not be diverted (3). The safeguard requirements and the ease of subversion of such provisions make many versions of the conventional processes subject to unacceptable proliferation risks. 

Wymer, R.G. Vondra, B.L. Historical development of the chemistry of aqueous reprocessing methods. In Light Water Reactor Nuclear Fuel Cycle] CRC Press, Inc. Boca Raton, FL, 1981 64-72. 

This is the length of time such that further cooling produces no appreciable reduction in the iodine activity. Shorter cooUng times are possible for aqueous reprocessing, because it is not necessary to reduce the activity to quite as low a level as the activity. 

J. M. Fletcher, in "Aqueous Reprocessing Chemistry," Symposium at Brussels, Belgium, 1963, Eurochemic. 

Modern Aqueous Reprocessing 14.5.1 Basic Commercial Process PUREX Process... 

Shibata, A. Kaji, N. Nakahara, M. Yano, K. Tayama, T. Nakamura, K Washiya, T. Myochin, M. Chikazawa, T. Kikuchi, T. (2009). Current Status on Research and Development of Uranium Crystallization System in Advanced Aqueous Reprocessing of FaCT Project, Proceedings of International Conference on The Nuclear Fuel Cycle Sustainable Options Industrial Perspectives (GLOBAL 2009), pp. 151-157, Paper 9154, Paris, France, September 6-11, 2009 Staritzky, E. Truitt, A. L. (1949). Optical and Norphological Crystallography of Plutonium Compounds, LA-745, Los Almos National Laboratory, Los Alamos, New Mexico, USA... 

Fuel cycle options, alternative Closed fuel cycle (U, MOX) graphite combustion or mechanical destraction before applying an aqueous reprocessing method... 

As an alternative, closed fuel cycles with MOX or hybrid U-Th fuel are considered for the GT-MHR. An option to apply fuel reprocessing is mentioned for the HTR-PM and the GTHTR-300 for the latter it has already been investigated. In case of TRISO coated particles, aqueous reprocessing methods (e.g., PUREX) cannot be applied directly. Specifically, the problem is with the SiC coating layers, which are not dissolved in mixtures of acids and, therefore, require a mechanical treatment to be removed. 

All liquid metal cooled SMRs are designed to operate in a closed nuclear fuel cycle providing for the use of non-aqueous reprocessing methods. The designs of KALIMER, MDP and PEACER make use of the ternary U-Pu-Zr or U-TRU-Zr fuel and pyro-metallurgical reprocessing. The RBEC-M and the Medium Scale Lead-bismuth Cooled Reactor are nitride fuel reactors. The BMN-170 offers flexibility in the selection of fuel with either oxide, or nitride, or metallic fuel being applicable. 

A closed fuel cycle is the alternative fuel cycle option. Aqueous reprocessing could be adopted to reprocess spent fuel from the CCR. Dry reprocessing, which is considered in application to the reduced moderation core [K-10], is also a candidate reprocessing option. An innovative fuel cycle system named BARS (BWR with an advanced recycle system) is proposed as a future fuel cycle option aimed at the enhanced utilization of uranium resources and reduction of radioactive wastes. In the BARS, the spent fuel from LWRs is recycled as a MOX fuel in BWR cores with the fast neutron spectrum, using dry reprocessing and vibro-packing for fabrication of the fuel. 

In the non-aqueous reprocessing process of spent nuclear fuels by pyrometallurgical and electrowinning methods [1, 2], a spent fuel is dissolved into molten LiCl-KCl or NaCl-CsCI eutectic melt and dissolved uranium and plutonium ions are recovered as metal or oxide. 

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