The Ceramic Waste Form Process at Idaho National Laboratory

Priebe, S.J.; Bateman, K. J.

doi:10.13182/nt08-a3948

“…36) The fabrication of ceramic waste from salt-loaded zeolite is to be demonstrated at an engineering scale in Idaho National Laboratory in U.S.A. 37) Hopefully, the salt treatment technology will be verified in the near future.…”

Section: Discussionmentioning

confidence: 99%

Recovery of Transuranium Elements from Real High-Level Liquid Waste by Pyropartitioning Process

Uozumi

¹

,

Iizuka

²

,

Kurata

³

et al. 2011

J. Nucl. Sci. Technol.

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A pyropartitioning process is under development to recover minor actinide elements from high-level liquid waste (HLLW) generated by Purex reprocessing. This pyropartitioning process consists of a denitration step that converts various elements in the HLLW into oxides, a chlorination step that converts the oxides into chlorides, and a reductive-extraction step that separates the actinide elements from fission products (FPs) in the chlorination product. The feasibility of each step was confirmed using simulating FPs and unirradiated transuranium elements (TRUs). In the present study, approximately 520 g of real HLLW was prepared to demonstrate the feasibility of the pyropartitioning process. Almost 100% of each TRU originally contained in the HLLW was recovered in the liquid cadmium phase in the reductive-extraction step, which showed that the expected chemical reactions were completed and the mass loss of TRUs was negligible in the denitration, chlorination, and reductive-extraction steps. The separation behaviors of actinide elements, including americium and curium, from FPs in the reductive-extraction step were quite similar to those observed in previous experiments using unirradiated materials. Hence, the pyropartitioning process was successfully verified.

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“…Although the recycling of the spent salt containing FPs was out of the scope of the present study, the spent salt treatment process using zeolite is under development. 36) The fabrication of ceramic waste from salt-loaded zeolite is to be demonstrated at an engineering scale in Idaho National Laboratory in U.S.A. 37) Hopefully, the salt treatment technology will be verified in the near future.…”

Section: Discussionmentioning

confidence: 99%

Recovery of Transuranium Elements from Real High-Level Liquid Waste by Pyropartitioning Process

Uozumi

¹

,

Iizuka

²

,

Kurata

³

et al. 2011

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

A pyropartitioning process is under development to recover minor actinide elements from high-level liquid waste (HLLW) generated by Purex reprocessing. This pyropartitioning process consists of a denitration step that converts various elements in the HLLW into oxides, a chlorination step that converts the oxides into chlorides, and a reductive-extraction step that separates the actinide elements from fission products (FPs) in the chlorination product. The feasibility of each step was confirmed using simulating FPs and unirradiated transuranium elements (TRUs). In the present study, approximately 520 g of real HLLW was prepared to demonstrate the feasibility of the pyropartitioning process. Almost 100% of each TRU originally contained in the HLLW was recovered in the liquid cadmium phase in the reductive-extraction step, which showed that the expected chemical reactions were completed and the mass loss of TRUs was negligible in the denitration, chlorination, and reductive-extraction steps. The separation behaviors of actinide elements, including americium and curium, from FPs in the reductive-extraction step were quite similar to those observed in previous experiments using unirradiated materials. Hence, the pyropartitioning process was successfully verified.

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“…(iii) Waste loaded BSG bonded apatite compositions (abbreviated as SrApCl þ x waste þ 20 BSG, x ¼ 10e16 wt.%) were prepared by weighing out required amounts of apatite forming reagents, glass forming reagents and a simulated chloride waste composition (2.63 wt% CeCl 3 þ 1.38 wt.% BaCl 2 þ 1.74 wt.% CsCl þ 11.23wt.% NaCl þ 12.08 wt.% NdCl 3 þ 70.91 wt% (LiCleKCl) eutectic) [2] in appropriate ratios (Tables 1 and 2), mixed, ground thoroughly and heated at 773e1023 K for 5 h in air in platinum boat/crucible. The chemical reaction is shown in Eq.…”

Section: Methodsmentioning

confidence: 99%