Current Status of Pyroprocessing Development at KAERI
Han-Soo Lee,Geun-Il Park,Jae-Won Lee,Kweon-Ho Kang,Jin-Mok Hur,Jeong-Guk Kim,Seungwoo Paek,In-Tae Kim,IL-Je Cho +8 more
TLDR
In this article, a pyroprocessing integrated inactive demonstration facility (PRIDE) was constructed at KAERI and it began test operation in 2012 to test the process regarding unit process performance, remote operation of equipments, integration of unit processes, scale-up of process, process monitoring, argon environment system operation, and safeguards related activities.Abstract:
Pyroprocessing technology has been actively developed at Korea Atomic Energy Research Institute (KAERI) to meet the necessity of addressing spent fuel management issue. This technology has advantages over aqueous process such as less proliferation risk, treatment of spent fuel with relatively high heat and radioactivity, and compact equipments. This paper describes the pyroprocessing technology development at KAERI from head-end process to waste treatment. The unit process with various scales has been tested to produce the design data associated with scale-up. Pyroprocess integrated inactive demonstration facility (PRIDE) was constructed at KAERI and it began test operation in 2012. The purpose of PRIDE is to test the process regarding unit process performance, remote operation of equipments, integration of unit processes, scale-up of process, process monitoring, argon environment system operation, and safeguards-related activities. The test of PRIDE will be promising for further pyroprocessing technology development.read more
Citations
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Reprocessing of spent nuclear fuel in India: Present challenges and future programme
TL;DR: In this paper, the authors have focused on the scientific and technological challenges associated with reprocessing of spent fuel from both the thermal and fast reactors, and the experience gained in the operation of reprocessed plants in the separation of the spent fuel of thermal reactors into uranium, plutonium and high level waste is described in detail.
Equilibrium Model for Ion Exchange Between Multivalent Cations and Zeolite-A in a Molten Salt
TL;DR: In this article, a two-site equilibrium model that accommodates divalent and trivalent cations for ion exchange between zeolite-A and molten chloride salts, a process being considered for concentrating nuclear fission products into high level waste forms, is presented.
Journal ArticleDOI
Selective morphological analysis of cerium metal in electrodeposit recovered from molten LiCl-KCl eutectic by radiography and computed tomography
TL;DR: In this paper, the surface morphology of metal extracted from a high temperature molten salt medium in the electrodeposit using x-ray radiography and computed tomography was analyzed for the first time.
Journal ArticleDOI
Application of multivariate analysis techniques to safeguards of the electrochemical treatment of used nuclear fuel
TL;DR: In this article, the authors used multivariate techniques to more accurately predict concentrations of multiple actinides from voltammetric data and demonstrated on experimental and simulated data for molten salt mixtures containing uranium and plutonium.
Journal ArticleDOI
Preparation of uranium(III) in a molten chloride salt: a redox mechanistic study
TL;DR: The most likely mechanism has been determined to involve the initial direct oxidation of uranium metal by Bi(III) to U(IV), which then reacts with unreacted uranium metal to form U(III).
References
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Nahum Andrés Medellín-Castillo,Roberto Leyva-Ramos,Raúl Ocampo-Pérez,Ramon F. Garcia De La Cruz,Antonio Aragón-Piña,Jose M. Martinez-Rosales,R.M. Guerrero-Coronado,Laura Fuentes-Rubio +7 more
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Preparation and Characterization of CaO Nanoparticles/NaX Zeolite Catalysts for the Transesterification of Sunflower Oil
Sandra Luz Martínez,Rubi Romero,José Carlos López,Amaya Romero,Víctor Sánchez Mendieta,Reyna Natividad +5 more
TL;DR: In this article, the results of the transesterification of sunflower oil with methanol to produce biodiesel using CaO nanoparticles supported on NaX zeolite as catalyst were reported.
Journal ArticleDOI
Immobilisation of radioactive waste in glasses, glass composite materials and ceramics
TL;DR: In this article, the basic principles of incorporating high level radioactive waste into glasses, ceramics and glass composites, including glass-ceramics, are described, and the importance of processing property-structure relations in such systems over size scales from the atomic to the geological and on timescales to hundreds of thousands of years is highlighted.
Journal ArticleDOI
Separation of Uranium and Transuranic Elements from Rare Earth Elements by Means of Multistage Extraction in LiCl-KCl/Bi System
Kensuke Kinoshita,Tadashi Inoue,S. P. Fusselman,D. L. Grimmett,J. J. Roy,C.L. Krueger,C. R. Nabelek,T.S. Storvick +7 more
TL;DR: In this paper, a pyrometallurgical partitioning process is developed for recovering transuranic elements (TRUs) from high-level liquid waste, and preliminary measurements are made of the distribution coefficients of TRUs in an LiCl-KCl/Bi system at 773 K. The experimental results agreed well with estimates obtained from measured separation factors for single-step reductive extraction.
Equilibrium Model for Ion Exchange Between Multivalent Cations and Zeolite-A in a Molten Salt
TL;DR: In this article, a two-site equilibrium model that accommodates divalent and trivalent cations for ion exchange between zeolite-A and molten chloride salts, a process being considered for concentrating nuclear fission products into high level waste forms, is presented.