Ammonium uranate hydrate wet reconversion process for the production of nuclear-grade UO2 powder from uranyl nitrate hexahydrate solution

Cited 0 time in webofscience Cited 0 time in scopus
  • Hit : 122
  • Download : 0
DC FieldValueLanguage
dc.contributor.authorLee, Byungkukko
dc.contributor.authorYang, Seungchulko
dc.contributor.authorKwak, Dongyongko
dc.contributor.authorJo, Hyunkwangko
dc.contributor.authorLee, Youngwooko
dc.contributor.authorBae, Youngmoonko
dc.contributor.authorLee, Jayhyungko
dc.date.accessioned2023-06-21T06:01:30Z-
dc.date.available2023-06-21T06:01:30Z-
dc.date.created2023-06-21-
dc.date.issued2023-06-
dc.identifier.citationNUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.6, pp.2206 - 2214-
dc.identifier.issn1738-5733-
dc.identifier.urihttp://hdl.handle.net/10203/307404-
dc.description.abstractThe existing wet reconversion processes for the recovery of scraps generated in manufacturing of nuclear fuel are complex and require several unit operation steps. In this study, it is attempted to simplify the recovery process of high-quality fuel-grade UO2 powder. A novel wet reconversion process for uranyl nitrate hexahydrate solution is suggested by using a newly developed pulsed fluidized bed reactor, and the resultant chemical characteristics are evaluated for the intermediate ammonium uranate hydrate product and subsequently converted UO2 powder, as well as the compliance with nuclear fuel specifications and advantages over existing wet processes. The UO2 powder obtained by the suggested process improved fuel pellet properties compared to those derived from the existing wet conversion processes. Powder performance tests revealed that the produced UO2 powder satisfies all specifications required for fuel pellets, including the sintered density, increase in re-sintered density, and grain size. Therefore, the processes described herein can aid realizing a simplified manufacturing process for nuclear-grade UO2 powders that can be used for nuclear power generation.(c) 2023 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).-
dc.languageEnglish-
dc.publisherKOREAN NUCLEAR SOC-
dc.titleAmmonium uranate hydrate wet reconversion process for the production of nuclear-grade UO2 powder from uranyl nitrate hexahydrate solution-
dc.typeArticle-
dc.identifier.wosid001002472700001-
dc.identifier.scopusid2-s2.0-85159187829-
dc.type.rimsART-
dc.citation.volume55-
dc.citation.issue6-
dc.citation.beginningpage2206-
dc.citation.endingpage2214-
dc.citation.publicationnameNUCLEAR ENGINEERING AND TECHNOLOGY-
dc.identifier.doi10.1016/j.net.2023.02.019-
dc.identifier.kciidART002964854-
dc.contributor.localauthorLee, Jayhyung-
dc.contributor.nonIdAuthorYang, Seungchul-
dc.contributor.nonIdAuthorKwak, Dongyong-
dc.contributor.nonIdAuthorJo, Hyunkwang-
dc.contributor.nonIdAuthorLee, Youngwoo-
dc.contributor.nonIdAuthorBae, Youngmoon-
dc.description.isOpenAccessN-
dc.type.journalArticleArticle-
dc.subject.keywordAuthorWet reconversion process-
dc.subject.keywordAuthorUranium dioxide-
dc.subject.keywordAuthorAmmonium uranate hydrate-
dc.subject.keywordAuthorPowder properties-
dc.subject.keywordPlusDIURANATE-
dc.subject.keywordPlusURANIUM-
Appears in Collection
CBE-Journal Papers(저널논문)
Files in This Item
There are no files associated with this item.

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0