Japan Nuclear Cycle Development Institute

The SETFICS process (Solvent Extraction for Trivalent /-elements Intragroup Separation in CMPO-Complexant System) was initially proposed by research teams of the former Japan Nuclear Cycle Development Institute (JNC, today JAEA) to separate An(III) from PUREX raffinates. It uses a TRUEX solvent (composed of CMPO and TBP, respectively dissolved at 0.2 and 1.2 M in -dodecane) to coextract trivalent actinides and lanthanides, and a sodium nitrate concentrated solution (4 M NaN03) containing DTPA (0.05 M) to selectively strip the TPEs at pH 2 and keep the Ln(III) extracted by the TRUEX solvent (239). However, the DFs for heavy Ln(III) are rather poor. An optimized version of the SETFICS process has recently been proposed as an alternative process to extraction chromatography for the recovery of Am(III) and Cm(III) in the New Extraction System for TRU Recovery (NEXT) process. NEXT basically consists of a front-end crystallization of uranium, a simplified PUREX process using TBP for the recovery of U, Np, and Pu, and a back-end Am(III) + Cm(III) recovery step (240, 241). 

The Japan Atomic energy Research Institue (JAERI) merged with the Japan Nuclear Cycle Development Institute... 

Organisation CRIEPI (Central Research Institute of Electric Power Industry), Hitachi (Hitachi Ltd), Toshiba (Toshiba Corporation), FES (Fuji Electric Systems Co.), INC (Japan Nuclear Cycle Development Institute), JAERI (Japan Atomic Energy Research Institute), MFH (Mitsubishi Heavy Industries, Ltd), ARTEC (Advanced Reactor Technology Co.), TGC (Tokyo Gas Co.), NSA (Nuclear Systems Association), Tokyo Tech (Tokyo Institute of Technology). 

A new thermochemical and electrolytic hybrid hydrogen production system in lower temperature range has been developed by the Japan Nuclear Cycle Development Institute (JNC) to achieve the hydrogen production from water by using the heat from a sodium cooled fast reactor (SFR) [7]. 

The thermochemical and electrolytic hybrid hydrogen production process has been developed by Japan Nuclear Cycle Development Institute (JNC). The process is based on sulfuric acid (H2SO4) syntliesis and decomposition process developed earlier (Westinghouse process) and sulfur trioxide (SO,) decomposition process is facilitated by electrolysis with ionic oxygen conductive solid electrolyte at 500°C-550°C. Stable hydrogen and oxygen production for several hours by the process was already confirmed in the experiments performed by JNC. 

A chopped irradiated fuel pin was transported to Alpha-Gamma Facility (AGF) of the Japan Nuclear Cycle Development Institute. The irradiated fuel was furtlicr sliced into pieces of 5 mm in length at AGF. 

JNC. 2000. HI2 Project to Establish the Scientific and Technical Basis for HLW Disposal in Japan. Second progress report on research and development for the geological disposal of HLW in Japan. Five volumes. Japan Nuclear Cycle Development Institute (JNC). 

This model was verified by desiccation tests performed by the Japan Nuclear Cycle Development Institute (INC 1999) with compacted samples of bentonite/sand mixture. A reversed correlation was derived to ht f x) = (s. Example 1 in... 

INC. 1999. H12 project to establish the scientific and technical basis for HLW disposal in Japan. Technical Report Support Report 2, Japan Nuclear Cycle Development Institute. http //www.jnc.go.jp/kaihatu/tisou/zh 12/h 12/s02 /pdf/b-09.pdf. 

Japan Nuclear Cycle Development Institute (JNC) has already developed the coupled thermo -hydro and mechanical (T-H-M) model and has initiated a research on the coupled T-H-M-C processes to predict the chemical evolution of buffer material and porewater chemistry, and the chemical effects on other (thermal, hydraulic and mechanical) processes. In this research, numerical experiment system for the coupled T-H-M-C processes is developed in order to predict the longterm evolution of the near-field (engineered barriers and surrounding host rock) for various repository designs and geological environments. 

This chapter shows the coupled thermal, hydraulic and mechanical behavior in the near field by using THAMES that is the finite element simulator originally developed by Ohnishi et al (1985). It was applied to the near field mesh shown as Figure 2. The model domain is corresponding to the shaded area shown in Figure 1. It is assumed that tunnel interval is 10 m and pit interval is 4.4 m following the Japan Nuclear Cycle Development Institute H12 report (JNC(1999)). 

Ibaraki University, Japan Japan Nuclear Cycle Development Institute, Japan Hazama Corporation, Japan ) Kyoto University, Japan... 

The experimental fast reactor JOYO at the Japan Nuclear Cycle Development Institute s Oarai Engineering Center attained initial criticality in April 1977 and was the first liquid metal cooled fast reactor in Japan. From 1983 to 2000, JOYO operated with the MK-II core as an irradiation test bed to develop the fuels and materials for future Japanese fast reactors. Thirty-five duty cycle operations and thirteen special tests with the MK-II core were completed by June 2000 without any fuel pin failures or serious plant trouble. The reactor is currently being upgraded to the MK-III core. This paper provides a review of the operational experiences obtained through the JOYO s operation. 

R.C. Arthur, H. Sasamoto, M. Shibata, M. Yui and A. Neyama, JNC TN8400 99-079, Japan Nuclear Cycle Development Institute, Japan, 1999. 

Japan Nuclear Cycle Development Institute, Technical reliability of high-level nuclear waste stratum disposal in Japan, JNC TN1400 99-020, 1999 (in Japanese). 

Japan Nuclear Cycle Development Institute, The Federation of Electric Power Companies of Japan Joint Team Concept Research Report on TRU Waste Disposal, JNC TY1400 2000-001, TRU TR-2000-01, 2000 (in Japanese). 

Japan Nuclear Cycle Development Institute, Japan... 

Kusama, M. Chikazawa, T. Tamaki, Y. (2005). Estimation Tests for Effecting Factor on Decontamination Property in Crystallization Process, JNC TJ8400 2005-006, Japan Nuclear Cycle Development Institute, Tokai, Ibaraki, Japan Lausch, J. Berg, R. Koch, L. Coquerelle, M. Glatz, J. P. Walker, C. T. Mayer, K. (1994). Dissolution Residues of Highly Burnt Nuclear Fuels. Journal of Nuclear Materials, Vol. 208, No. 1-2, (January 1994), pp. 73-80, ISSN 0022-3115... 

To accomplish this plan, the sodium cooled experimental reactor JOYO is now under operation in the Japan Atomic Energy Agency (JAEA), a new organization combining the former Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI). The JOYO reactor is being operated to develop and validate sodium, fuel, and material technologies, etc. 

The Japan Nuclear Cycle Development Institute (JNC) is developing the medium scale lead-bismuth cooled reactor see Annex XXV. It is a tank type modular design without intermediate heat transport system. The module power is 710 MW(e), and the plant of 4 modules with 2840 MW(e) total electric output was selected as basic. The medium scale lead-bismuth cooled reactor is at the conceptual design stage. 

Recently, the work towards elaboration of the RBEC-M concept was stimulated by the exchange of scientific and technical information with the domestic and foreign organizations developing new reactors with liquid heavy metal coolants. In particular, the French Commissariat a I Energie Atomique (CEA) and the Japan Nuclear Cycle Development Institute (JNC) could be mentioned in this context. 

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