Advanced orient cycle - Progress on Fission Product separation and utilization

Isao Yamagishi, Masaki Ozawa, Hitoshi Mimura, Shohei Kanamura, Koji Mizuguchi

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

Fission reaction of U-235 and/or plutonium generates more than 40 elements and 400 nuclides in the spent fuel. Among them, 31 elements are categorized as rare metals. In a conventional fuel cycle U and Pu are reused but others are vitrified for disposal. Adv.-ORIENT (Advanced Optimization by Recycling Instructive Elements) Cycle strategy was drawn up for the minimization of radio-toxicity and volume of radioactive waste as well as the utilization of valuable elements/nuclides in the waste. The present paper describes the progress on Fission Products (FP) separation in this Cycle. Highly functional inorganic adsorbent (AMP-SG, silica gel loaded with ammonium molybdophosphate) and organic microcapsule (CE-ALG, alginate gel polymer enclosed with crown ether D18C6) were developed for separation of heat-generating Cs and Sr nuclides, respectively. The AMP-SG adsorbed more than 99% of Cs selectively from a simulated High-level Liquid Waste (HLLW). The ALG microcapsule adsorbed 0.0249 mmol/g of Sr and exhibited the order of its selectivity; Ba > Sr > Pd >> Ru > Rb > Ag. The electrodeposition is advantageous for both recovery and utilization of PGMs (Ru, Rh, Pd) and Tc because PGMs are recovered as metal on Pt electrode. Among PGMs, Pd was easily deposited on the Pt electrode. In the presence of Pd or Rh the reduction of Ru and Tc was accelerated more in hydrochloric acid media than in nitric acid. In the simulated HLLW, the redox reaction of Fe(III)/Fe(II) disturbed deposition of elements except for Pd. The deposits on Pt electrode showed higher catalytic reactivity on electrolytic hydrogen production than the original Pt electrode. The reactivity of deposits prepared from the simulated HLLW was higher than that from solution containing only PGM.

Original languageEnglish
Title of host publicationASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM2010
Pages107-116
Number of pages10
DOIs
Publication statusPublished - 2010 Dec 1
EventASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM2010 - Tsukuba, Japan
Duration: 2010 Oct 32010 Oct 7

Publication series

NameProceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM
Volume2

Other

OtherASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM2010
CountryJapan
CityTsukuba
Period10/10/310/10/7

Keywords

  • Adsorption
  • Cesium
  • Electrolysis
  • Nuclear waste
  • PGM
  • Palladium
  • Rhodium
  • Ruthenium
  • Separation
  • Strontium
  • Technetium
  • Utilization

ASJC Scopus subject areas

  • Safety, Risk, Reliability and Quality
  • Energy Engineering and Power Technology
  • Waste Management and Disposal

Fingerprint Dive into the research topics of 'Advanced orient cycle - Progress on Fission Product separation and utilization'. Together they form a unique fingerprint.

  • Cite this

    Yamagishi, I., Ozawa, M., Mimura, H., Kanamura, S., & Mizuguchi, K. (2010). Advanced orient cycle - Progress on Fission Product separation and utilization. In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, ICEM2010 (pp. 107-116). (Proceedings of the International Conference on Radioactive Waste Management and Environmental Remediation, ICEM; Vol. 2). https://doi.org/10.1115/ICEM2010-40053