Published September 2011 | Version v1
Journal article

Current status and future plans of Advanced ORIENT Cycle strategy

  • 1. Tokai Research and Development Center, Japan Atomic Energy Agency, 2-4 Shirane Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195 (Japan)
  • 2. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
  • 3. Tohoku University, Aramaki-Aza-Aoba 6-6-01-2, Aoba-ku, Sendai 980-8579 (Japan)
  • 4. Toshiba Corporation Power Systems Company, 4-1, Ukishimacho, Kawasaki-ku, Kawasaki 210-0862 (Japan)
  • 5. Kaken Co., Ltd., 1044 Horimachi, Mito, Ibaraki 310-0903 (Japan)
  • 6. National Institute of Advanced Industrial Science and Technology (AIST), AIST Tsukuba Central 5, 1-1-1 Higashi, Tsukuba, Ibaraki 305-8565 (Japan)

Description

For minimization of the ecological risks inherent in nuclear fuel recycling, a new fuel cycle paradigm was proposed and its key technology developments have been carried out as a part of the Advanced Optimization by Recycling Instructive Elements (Adv.-ORIENT) Cycle strategy. The basic concept of the Adv.-ORIENT Cycle uses a three-pronged approach, separation, transmutation and utilization of nuclides and elements, based on the FBR fuel cycle. Fundamental research studies done in Adv.-OEIENT Cycle [Phase-1: 2006–2010] have led to the following findings.1.Cs and Sr separation and its utilization: Silica gel loaded with ammonium molybdophosphate (AMP) and hybrid organic microcapsules with crown ether D18C6 were investigated to chromatographically separate Cs and Sr, respectively. In particular, uptake experiments of Cs from solution simulating the spent fuel solution obtained were carried out by a batch method, and the uptake rates achieved were more than 90%. 2.Minor actinide (MA)/lanthanide/fission product (FP) separation: A tertiary pyridine type resin (TPR) can be used to recover Am, Cm and lantanide elements with a high separation factor by a chromatographic method from spent fuel solution. The TPR can be used with hydrochloric acid (HCl) as well as nitric acid (HNO3). 3.Ru, Ph, Pd and Tc separation: A catalytic electrolytic extraction (CEE) method can effectively separate Ru, Ph, Pd and Tc. High recovery ratios of Ru, Rh, Pd, Tc, Se, etc. were achieved using HCl solutions. Rh co-deposition significantly accelerated reduction of Ru, Tc and Re using HNO3 solutions. 4.Ru, Ph, Pd and Tc utilization: Based on the mixed deposit obtained from the CEE experiments, Ru/Rh/Pd/Tc(Re)-Pt electrodes provided the highest catalytic reactivity in the electrolytic production of hydrogen in an alkali solution. 5.Basic engineering research: Results of corrosion experiments showed that Hastelloy-B and Ta had a good anti-corrosive property in a wide range of HCl concentrations. The basic thermo-chemical stability of TPR and tri-butyl phosphorous (TBP, as a reference) was also experimentally studied, and the process safety conditions to be specified for practical use of TPR could be identified.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.pnucene.2011.04.018

Additional details

Identifiers

DOI
10.1016/j.pnucene.2011.04.018;
PII
S014919701100076X;

Publishing Information

Journal Title
Progress in Nuclear Energy
Journal Volume
53
Journal Issue
7
Journal Page Range
p. 980-987
ISSN
0149-1970

Optional Information

Notes
Copyright © 2011 Elsevier Ltd. All rights reserved.