Chemical partitioning technologies for an ATW system

Laidler, J.J.; Burris, L.; Collins, E.D.; Duguid, J.O.; Henry, R.N.; Hill, J.G.; Karell, E. J.; McDeavitt, Sean M.; Thompson, M.L.; Williamson, Mark A.; Willit, James L.

doi:10.1016/s0149-1970(00)00096-2

Cited by 25 publications

(9 citation statements)

References 1 publication

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“…High-level radioactive wastes generated during the electrometallurgical reprocessing of nuclear fuel to recycle U and transuranic elements will be immobilized in durable waste forms to facilitate handling, storage, transport, and final disposal in a geological repository [1,2]. The two principal high-level radioactive waste streams are salt waste contaminated with oxidized fission products and metallic waste comprised of activated cladding hulls and metallic fission products not oxidized under the processing conditions [3].…”

Section: Introductionmentioning

confidence: 99%

Formation and corrosion of a 410 SS/ceramic composite

Chen

Ebert

Indacochea

2016

Journal of Nuclear Materials

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This study addressed the possible use of alloy/ceramic composite waste forms to immobilize metallic and oxide waste streams generated during the electrochemical reprocessing of spent reactor fuel using a single waste form. A representative composite material was made to evaluate the microstructure and corrosion behavior at alloy/ceramic interfaces by reacting 410 stainless steel with Zr, Mo, and a mixture of lanthanide oxides. Essentially all of the available Zr reacted with lanthanide oxides to generate lanthanide zirconates, which combined with the unreacted lanthanide oxides to form a porous ceramic network that filled with alloy to produce a composite puck. Alloy present in excess of the pore volume of the ceramic generated a metal bead on top of the puck. The alloys in the composite and forming the bead were both mixtures of martensite grains and ferrite grains bearing carbide precipitates; FeCrMo intermetallic phases also precipitated at ferrite grain boundaries within the composite puck. Micrometer-thick regions of ferrite surrounding the carbides were sensitized and corroded preferentially in electrochemical tests. The lanthanide oxides dissolved chemically, but the lanthanide zirconates did not dissolve and are suitable host phases. The presence of oxide phases did not affect corrosion of the neighboring alloy phases.

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Section: Introductionmentioning

confidence: 99%

Formation and corrosion of a 410 SS/ceramic composite

Chen

Ebert

Indacochea

2016

Journal of Nuclear Materials

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“…The technology promises important advantages when combined with a metal fuel fast reactor [1][2][3][4][5]. The electrochemical process based on Li reduction in Li 2 O-LiCl molten salt has been regarded as a promising technology for the metallization of uranium [2,[6][7][8][9].…”

Section: Introductionmentioning

confidence: 99%

Application of a boron doped diamond (BDD) electrode as an anode for the electrolytic reduction of UO2 in Li2O–LiCl–KCl molten salt

Park

Kim

Hur

et al. 2013

Journal of Nuclear Materials

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“…The behavior in PBT of the spent fuel management strategy, proposed by (Tálamo et al, 2004, Rodriguez et al, 2003 for the so called Deep Burn Modular Helium Reactor (DB-MHR) are analyzed. Three strategies for fuel management are compared: first of all, the traditional one, named "spent fuel"(SF) that uses spent fuel from LWR Second, the one in which the transuranic elements are divided in two groups, a "Driven Fuel" (DF) composed only by Plutonium isotopes and Np is used in PBT core like SF, and third, the fuel management strategy in which after the DF has reached the stationary state we feed PBT core with a layer of "Transmutation Fuel" (TF), composed by Am 241 , Am 243 and Cm 244 isotopes from spent DF and it is mixed after discharge from the reactor core with the Am and Cm isotopes, which were set-aside after UREX process (Laidler et al, 2001).…”

Section: Introductionmentioning

confidence: 99%

Performance of a transmutation advanced device for sustainable energy application

Garcı́a

Rosales

García

et al. 2011

Progress in Nuclear Energy

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Keywords:Very high temperature reactor Nuclear waste Transmutation Preliminary studies have been performed to design a device for nuclear waste transmutation and hydrogen generation based on a gas-cooled pebble bed accelerator driven system, TADSEA (Transmutation Advanced Device for Sustainable Energy Application). In previous studies we have addressed the viability of an ADS Transmutation device that uses as fuel wastes from the existing LWR power plants, encapsulated in graphite in the form of pebble beds, cooled by helium which enables high temperatures (in the order of 1200 K), to generate hydrogen from water either by high temperature electrolysis or by thermochemical cycles. For designing this device several configurations were studied, including several reflectors thickness, to achieve the desired parameters, the transmutation of nuclear waste and the production of 100 MW of thermal power. In this paper new studies performed on deep burn in-core fuel management strategy for LWR waste are presented. The fuel cycle on TADSEA device has been analyzed based on both: driven and transmutation fuel that had been proposed by the General Atomic design of a gas turbine-modular helium reactor. The transmutation results of the three fuel management strategies, using driven, transmutation and standard LWR spent fuel were compared, and several parameters describing the neutron performance of TADSEA nuclear core as the fuel and moderator temperature reactivity coefficients and transmutation chain, are also presented.

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Chemical partitioning technologies for an ATW system

Cited by 25 publications

References 1 publication

Formation and corrosion of a 410 SS/ceramic composite

Formation and corrosion of a 410 SS/ceramic composite

Application of a boron doped diamond (BDD) electrode as an anode for the electrolytic reduction of UO2 in Li2O–LiCl–KCl molten salt

Performance of a transmutation advanced device for sustainable energy application

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