Dissolution study of spent PWR fuel: Dissolution behavior and chemical properties of insoluble residues

Adachi, T.; Ohnuki, Mamoru; Yoshida, Naoki; Sonobe, Tamotsu; Kawamura, Wataru; Takeishi, Hideyo; Gunji, Katsubumi; Kimura, Takashi; Suzuki, Toshio; Nakahara, Y.; Muromura, Tadasumi; Kobayashi, Yasuko; Okashita, Hiroshi; Yamamoto, Toshio

doi:10.1016/0022-3115(90)90421-i

Cited by 54 publications

(33 citation statements)

References 15 publications

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“…Many authors have reported the particle size and chemical composition of this phase [9][10][11][12][13][14][15]. The reported composition is variable, but tends to be largely Mo and Ru with smaller amounts of Tc, Rh, and Pd.…”

Section: Introductionmentioning

confidence: 93%

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Soderquist

Hanson

2010

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 93%

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Soderquist

Hanson

2010

Journal of Nuclear Materials

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“…It should be emphasized that the experimentally determined ratios of the fission products in the precipitates differ substantially from those calculated for the fuel [11]. For example, for a fuel with a burn-up of 31.4 MW day kg !1 of U, the calculated proportion, %, of the elements was 42, 25, 16, 10, and 7% for Mo, Ru, Pd, Tc, and Rh, respectively, against 23.6, 58.0, 8.9, 1.1, and 8.3%, respectively, as determined experimentally for the precipitates.…”

Section: Speciation Of Palladium In Irradiated Fuel and Reprocessing mentioning

confidence: 95%

Palladium in Irradiated Fuel. Are There Any Prospects for Recovery and Application?

Pokhitonov

Romanovskii

2005

Radiochemistry

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Published data on the speciation and behavior of Pd in different stages of reprocessing of irradiated fuel from NPPs were analyzed. Various methods for recovering Pd from solutions and solids of different compositions, arising in reprocessing, were described. The Pd sales volumes in the recent decades were reported, and possible industrial and technical applications of Pd were discussed. An opinion is expressed that it is of interest to recover [reactor-grade] Pd to be used in reprocessing of the waste from radiochemical enterprises (e.g., immobilization of 129 I and/or TPEs), i.e., in processes where the presence of radioactive nuclide 107 Pd does not matter and exhaustive removal of other fission products is not required.The history of science and technology abounds in cases where ideas, set aside many years ago, are revived. This is true of the attempted recovery of platinum group metals (PGMs) from irradiated fuel of NPPs. The first relevant publications [133] appeared about 50 years ago, and their authors considered it very attractive to find the possibilities of recovering Pd and Rh whose yield in uranium fission products is fairly high, namely, kilograms per ton of fuel. But as yet, no country has succeeded in developing an acceptable method for commercial recovery of platinum metals from real radioactive solutions. This is due to a number of reasons.The main purpose of irradiated nuclear fuel reprocessing is to recover U and Pu and to localize fission products, rather than to recover individual radionuclides intended for commercial purposes. On the other hand, the use of any radionuclides, even minimally active, is extremely negatively received by the public. Probably, this is the most significant negative factor that questions the appearance of a demand for [reactor-grade] Pd or Rh in their traditional application spheres, even if they will be cheaper than Pd and Rh extracted from ores.At the same time, depletion of mineral resources of platinum metals will sooner or later cause their prices to rise to the level when irradiated fuel could become a real substitute to their commercial production sources. Since recently, technologies for high-level waste (HLW) partitioning have been developed, which would yield solutions that are less active and simpler in composition than the first extraction cycle raffinates containing all the fission products and, thus, will be suitable for recovery of Pd and Rh.In this work, we analyzed publications on recovery of Pd from irradiated fuel. Since the prospects for commercial recovery of Pd are directly related to technical demands and natural reserves, we considered it necessary to supplement this review with a section devoted to possible applications of Pd and its compounds.

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“…Zirconium and Mo precipitate in the form of zirconium molybdate in the dissolution process (Adachi et al, 1990;Lausch et al, 1994;Usami et al, 2010). This compound tends to form at high temperature and with low HNO 3 concentration in the solution.…”

Section: Separation Of Uranyl Nitrate Hexahydrate Crystal From Dissolmentioning

confidence: 99%

Separation of Uranyl Nitrate HexahydrateCrystal from Dissolver Solution of IrradiatedFast Neutron Reactor Fuel

Nakahara¹

2012

Advances in Crystallization Processes

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Dissolution study of spent PWR fuel: Dissolution behavior and chemical properties of insoluble residues

Cited by 54 publications

References 15 publications

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Palladium in Irradiated Fuel. Are There Any Prospects for Recovery and Application?

Separation of Uranyl Nitrate HexahydrateCrystal from Dissolver Solution of IrradiatedFast Neutron Reactor Fuel

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