Method of reprocessing spent nuclear fuel
66 Most part of an amount of uranium contained in the spent nuclear fuel is removed by making fluorine or a fluorochemical act on the spent nuclear fuel to convert the uranium into UF, and the uranium is purified through a simple method of distilling the UFtogether with a absorbent. After removing t...
Saved in:
Main Authors | , , , , |
---|---|
Format | Patent |
Language | English |
Published |
04.11.2008
|
Online Access | Get full text |
Cover
Loading…
Abstract | 66 Most part of an amount of uranium contained in the spent nuclear fuel is removed by making fluorine or a fluorochemical act on the spent nuclear fuel to convert the uranium into UF, and the uranium is purified through a simple method of distilling the UFtogether with a absorbent. After removing the most part of the amount of uranium, the remaining nuclear fuel material is dissolved and then transferred to an extraction process to recover plutonium. By doing so, a small sized dry process can be employed as a uranium purification process. Since the nuclear fuel material is dissolved and extracted after removing most part of an amount of uranium, a volume of processing solution can be reduced and the machine installation scale can be made small. Accordingly, the reprocessing facility can be extremely downsized. |
---|---|
AbstractList | 66 Most part of an amount of uranium contained in the spent nuclear fuel is removed by making fluorine or a fluorochemical act on the spent nuclear fuel to convert the uranium into UF, and the uranium is purified through a simple method of distilling the UFtogether with a absorbent. After removing the most part of the amount of uranium, the remaining nuclear fuel material is dissolved and then transferred to an extraction process to recover plutonium. By doing so, a small sized dry process can be employed as a uranium purification process. Since the nuclear fuel material is dissolved and extracted after removing most part of an amount of uranium, a volume of processing solution can be reduced and the machine installation scale can be made small. Accordingly, the reprocessing facility can be extremely downsized. |
Author | Sasahira, Akira Takahashi, Masanori Shibata, Youji Fukasawa, Tetsuo Kamoshida, Mamoru |
Author_xml | – sequence: 1 givenname: Tetsuo surname: Fukasawa fullname: Fukasawa, Tetsuo – sequence: 2 givenname: Masanori surname: Takahashi fullname: Takahashi, Masanori – sequence: 3 givenname: Youji surname: Shibata fullname: Shibata, Youji – sequence: 4 givenname: Akira surname: Sasahira fullname: Sasahira, Akira – sequence: 5 givenname: Mamoru surname: Kamoshida fullname: Kamoshida, Mamoru |
BookMark | eNrjYmDJy89L5WTQ9E0tychPUchPUyhKLSjKT04tLs7MS1coLkjNK1HIK03OSU0sUkgrTc3hYWBNS8wpTuWF0twMCm6uIc4euqXFBYklQNXF8elFiSDKwNzExNTczMCYCCUAyxoraA |
ContentType | Patent |
CorporateAuthor | Hitachi-GE Nuclear Energy, Ltd |
CorporateAuthor_xml | – name: Hitachi-GE Nuclear Energy, Ltd |
DBID | EFH |
DatabaseName | USPTO Issued Patents |
DatabaseTitleList | |
Database_xml | – sequence: 1 dbid: EFH name: USPTO Issued Patents url: http://www.uspto.gov/patft/index.html sourceTypes: Open Access Repository |
DeliveryMethod | fulltext_linktorsrc |
ExternalDocumentID | 07445760 |
GroupedDBID | EFH |
ID | FETCH-uspatents_grants_074457603 |
IEDL.DBID | EFH |
IngestDate | Sun Mar 05 22:31:58 EST 2023 |
IsOpenAccess | true |
IsPeerReviewed | false |
IsScholarly | false |
Language | English |
LinkModel | DirectLink |
MergedId | FETCHMERGED-uspatents_grants_074457603 |
OpenAccessLink | https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/7445760 |
ParticipantIDs | uspatents_grants_07445760 |
PatentNumber | 7445760 |
PublicationCentury | 2000 |
PublicationDate | 20081104 |
PublicationDateYYYYMMDD | 2008-11-04 |
PublicationDate_xml | – month: 11 year: 2008 text: 20081104 day: 04 |
PublicationDecade | 2000 |
PublicationYear | 2008 |
References | "Purification Process studies for the Reprocessing by Fluoride Volatility Method", JAERI-M6592, pp. 1-44, Japan Atomic Energy, Research Institute, 1976, no month. "Present Status and Problems on Non-Aqueous Reprocessing" by Special Committee on Non-aqueous Reprocessing, Journal of the Atomic Energy Society of Japan, vol. 9, No. 9, pp. 14-19 (1967), no month. (09138297) 19970500 (925178) 19630500 Levenson et al. (4278559) 19810700 "Safeguards and Nonproliferation Aspects of a Dry Fuel Recycling Technology", 1993, vol. 2, pp. 715-721, no month. Ruiz et al. (4011296) 19770300 (1129855) 19681000 Alter et al. (3359078) 19671200 Katz et al. (2830873) 19580400 Cathers et al. (3275422) 19660900 Jonke et al. (3294493) 19661200 |
References_xml | – year: 19660900 ident: 3275422 contributor: fullname: Cathers et al. – year: 19671200 ident: 3359078 contributor: fullname: Alter et al. – year: 19770300 ident: 4011296 contributor: fullname: Ruiz et al. – year: 19661200 ident: 3294493 contributor: fullname: Jonke et al. – year: 19630500 ident: 925178 – year: 19970500 ident: 09138297 – year: 19681000 ident: 1129855 – year: 19810700 ident: 4278559 contributor: fullname: Levenson et al. – year: 19580400 ident: 2830873 contributor: fullname: Katz et al. |
Score | 2.7159393 |
Snippet | 66 Most part of an amount of uranium contained in the spent nuclear fuel is removed by making fluorine or a fluorochemical act on the spent nuclear fuel to... |
SourceID | uspatents |
SourceType | Open Access Repository |
Title | Method of reprocessing spent nuclear fuel |
URI | https://image-ppubs.uspto.gov/dirsearch-public/print/downloadPdf/7445760 |
hasFullText | 1 |
inHoldings | 1 |
isFullTextHit | |
isPrint | |
link | http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwfV1NSwMxEB1qEbQnRcX6RQ5ePKxud5Pt9ixdFqHSg0JvZZPMeqnZZT_o33cmldKLXpPwkhAmMxPevAA8mhnqhKt7IpVSgqKtJpsLVZBgZFgQLi4mXJy8eE_yT_m2UqsB5PtamG8yo6CmtbTPfVt3lSdX0vW-O_hgJ_7MGoGO1Qe2blMVdmnLl6mUFDpT8n6Uhkztm2f5CE4IgkI217UHTiM7g-Olbz2HAboLeFr4z5pFVQpWkvT8fPIboq1pjHCsK1w0ouxxcwkim3-85sEed_3VMF9lHf7OH1_BkPJ2vAYx1dbIUsVkJVbqOEqNMgkWysjZxCKqMYz_hLn5p-8WTj1pgd825R0Mu6bHe_KMnX7w2_4BFGdutw |
link.rule.ids | 230,309,783,805,888,64374 |
linkProvider | USPTO |
linkToPdf | http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwfV1LT8MwDLamgWCcQIAYzxy4cChsbdJtZ1jVDTb1ANJuVfMol5FWfYi_PztDExe4JpFlJXJsJ58_A9yriZEhVff4YowJitQSbW4gvND4igjhgmxIxcmLZRh_8PlKrDoQ72phvtCMvBJ1qR_bumwKB67E63178N6W_Jk4Ai2xD3zbdZHpROdPI84xdMbkfY--oohFfxrFR3CIQjBos039y21Ex7CfuNET6Bh7Cg8L166ZFTkjLkmH0EfPweoS1zBLzMJZxfLWrM-ARdP359jbyU0_K0KspIMfDYJz6GLmbi6AjaRWPBcB2onmMvDHSqjQZELxyVAbI_rQ_1PM5T9zd3CQvETp22z5egU9h2Cgh05-Dd2mas0NuslG3rod2ACvUXGy |
openUrl | ctx_ver=Z39.88-2004&ctx_enc=info%3Aofi%2Fenc%3AUTF-8&rfr_id=info%3Asid%2Fsummon.serialssolutions.com&rft_val_fmt=info%3Aofi%2Ffmt%3Akev%3Amtx%3Apatent&rft.title=Method+of+reprocessing+spent+nuclear+fuel&rft.inventor=Fukasawa%2C+Tetsuo&rft.inventor=Takahashi%2C+Masanori&rft.inventor=Shibata%2C+Youji&rft.inventor=Sasahira%2C+Akira&rft.inventor=Kamoshida%2C+Mamoru&rft.number=7445760&rft.date=2008-11-04&rft.externalDBID=n%2Fa&rft.externalDocID=07445760 |