A benchtop comparison of drying methods relevant to failed spent nuclear fuel

A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of...

Full description

Saved in:
Bibliographic Details
Published inProgress in nuclear energy (New series) Vol. 115; pp. 120 - 125
Main Authors Goode, James B., Hambley, David I., Hanson, Bruce C.
Format Journal Article
LanguageEnglish
Published Oxford Elsevier Ltd 01.08.2019
Elsevier BV
Subjects
Online AccessGet full text
ISSN0149-1970
1878-4224
DOI10.1016/j.pnucene.2019.03.025

Cover

Abstract A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of stainless steel clad Advanced Gas-cooled Reactor fuel. A large number of tests have been carried out using the same small scale simulated fuel pin. The overall results suggest that the drying rate obtained from vacuum drying is significantly higher than when carrying out flowed gas drying. When energy usage is accounted for the drying efficiency is increased still further. Testing also considered different defects; pinholes and stress corrosion cracks. Despite the theoretical open area of the crack being potentially greater than for a pinhole, the pinholed samples were found to have a considerably higher drying rate.
AbstractList A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of stainless steel clad Advanced Gas-cooled Reactor fuel. A large number of tests have been carried out using the same small scale simulated fuel pin. The overall results suggest that the drying rate obtained from vacuum drying is significantly higher than when carrying out flowed gas drying. When energy usage is accounted for the drying efficiency is increased still further. Testing also considered different defects; pinholes and stress corrosion cracks. Despite the theoretical open area of the crack being potentially greater than for a pinhole, the pinholed samples were found to have a considerably higher drying rate.
A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming closure of the Thorp reprocessing facility at Sellafield, UK. Drying will be needed ahead of disposal possibly ahead of dry interim storage of stainless steel clad Advanced Gas-cooled Reactor fuel. A large number of tests have been carried out using the same small scale simulated fuel pin. The overall results suggest that the drying rate obtained from vacuum drying is significantly higher than when carrying out flowed gas drying. When energy usage is accounted for the drying efficiency is increased still further. Testing also considered different defects; pinholes and stress corrosion cracks. Despite the theoretical open area of the crack being potentially greater than for a pinhole, the pinholed samples were found to have a considerably higher drying rate.
Author Hambley, David I.
Goode, James B.
Hanson, Bruce C.
Author_xml – sequence: 1
  givenname: James B.
  orcidid: 0000-0002-4900-7153
  surname: Goode
  fullname: Goode, James B.
  email: james.goode@nnl.co.uk
  organization: National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG, UK
– sequence: 2
  givenname: David I.
  surname: Hambley
  fullname: Hambley, David I.
  organization: National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG, UK
– sequence: 3
  givenname: Bruce C.
  surname: Hanson
  fullname: Hanson, Bruce C.
  organization: School of Chemical and Process Engineering, University of Leeds, Leeds, LS2 9JT, UK
BookMark eNqFkE1LAzEQhoNUsFZ_ghDwvGuy2exm8SBF_IKKFz2HbDJrU7bJmqSC_96UevLS0zAwzzszzzmaOe8AoStKSkpoc7MpJ7fT4KCsCO1KwkpS8RM0p6IVRV1V9QzNCa27gnYtOUPnMW4IoS3lfI5el7gHp9fJT1j77aSCjd5hP2ATfqz7xFtIa28iDjDCt3IJJ48HZUcwOE6Q-7x6BBXwsIPxAp0Oaoxw-VcX6OPx4f3-uVi9Pb3cL1eFZqxNBddGi8ZQna-nHGCgA8vH9l3LaypMLzTjoh4EYY0wlepZAz0RvFOkqRitDVug60PuFPzXDmKSG78LLq-UVcVJhmtO8tTtYUoHH2OAQWqbVLLepZA_kJTIvT-5kX_-5N6fJExmf5nm_-gp2K0KP0e5uwMHWcC3hSCjtlkxGBtAJ2m8PZLwCx2Lj0c
CitedBy_id crossref_primary_10_1016_j_net_2024_103430
crossref_primary_10_1016_j_pnucene_2019_04_004
Cites_doi 10.1080/07373939808917423
10.1016/j.pnucene.2018.07.011
ContentType Journal Article
Copyright 2019 Elsevier Ltd
Copyright Elsevier BV Aug 2019
Copyright_xml – notice: 2019 Elsevier Ltd
– notice: Copyright Elsevier BV Aug 2019
DBID AAYXX
CITATION
7TB
8FD
FR3
KR7
DOI 10.1016/j.pnucene.2019.03.025
DatabaseName CrossRef
Mechanical & Transportation Engineering Abstracts
Technology Research Database
Engineering Research Database
Civil Engineering Abstracts
DatabaseTitle CrossRef
Civil Engineering Abstracts
Engineering Research Database
Technology Research Database
Mechanical & Transportation Engineering Abstracts
DatabaseTitleList Civil Engineering Abstracts

DeliveryMethod fulltext_linktorsrc
Discipline Engineering
EISSN 1878-4224
EndPage 125
ExternalDocumentID 10_1016_j_pnucene_2019_03_025
S0149197019300903
GroupedDBID --K
--M
.~1
0R~
123
1B1
1~.
1~5
29P
4.4
457
4G.
5VS
7-5
71M
8P~
9JN
AACTN
AAEDT
AAEDW
AAHCO
AAIAV
AAIKJ
AAKOC
AALRI
AAOAW
AAQFI
AAQXK
AARJD
AAXUO
ABEFU
ABFNM
ABMAC
ABXDB
ABYKQ
ACDAQ
ACGFS
ACIWK
ACRLP
ADBBV
ADEZE
ADMUD
AEBSH
AEKER
AENEX
AFFNX
AFKWA
AFTJW
AGHFR
AGUBO
AGYEJ
AHHHB
AHIDL
AIEXJ
AIKHN
AITUG
AJBFU
AJOXV
ALMA_UNASSIGNED_HOLDINGS
AMFUW
AMRAJ
ASPBG
AVWKF
AXJTR
AZFZN
BELTK
BKOJK
BLXMC
CS3
DU5
EBS
EFJIC
EFLBG
EJD
EO8
EO9
EP2
EP3
FDB
FGOYB
FIRID
FNPLU
FYGXN
G-2
G-Q
GBLVA
HZ~
IHE
J1W
JARJE
KOM
LY6
M41
MO0
N9A
O-L
O9-
OAUVE
OZT
P-8
P-9
PC.
Q38
R2-
RIG
ROL
RPZ
SAC
SDF
SDG
SES
SEW
SPC
SPCBC
SPD
SSR
SSZ
T5K
TN5
WUQ
~02
~G-
AATTM
AAXKI
AAYWO
AAYXX
ABWVN
ACRPL
ACVFH
ADCNI
ADNMO
AEIPS
AEUPX
AFJKZ
AFPUW
AFXIZ
AGCQF
AGQPQ
AGRNS
AIGII
AIIUN
AKBMS
AKRWK
AKYEP
ANKPU
APXCP
BNPGV
CITATION
SSH
7TB
8FD
EFKBS
FR3
KR7
ID FETCH-LOGICAL-c337t-5cdc86d1c01615eef1f3187b975418db8c3584f80368d2ab36eb0859a062314d3
IEDL.DBID AIKHN
ISSN 0149-1970
IngestDate Sun Jul 13 04:49:04 EDT 2025
Thu Apr 24 22:56:00 EDT 2025
Tue Jul 01 01:01:51 EDT 2025
Fri Feb 23 02:34:25 EST 2024
IsPeerReviewed true
IsScholarly true
Keywords Pinholes
Cracks
Nuclear fuel
Dry storage
AGR
Stainless steel
Language English
LinkModel DirectLink
MergedId FETCHMERGED-LOGICAL-c337t-5cdc86d1c01615eef1f3187b975418db8c3584f80368d2ab36eb0859a062314d3
Notes ObjectType-Article-1
SourceType-Scholarly Journals-1
ObjectType-Feature-2
content type line 14
ORCID 0000-0002-4900-7153
PQID 2250584450
PQPubID 2045411
PageCount 6
ParticipantIDs proquest_journals_2250584450
crossref_citationtrail_10_1016_j_pnucene_2019_03_025
crossref_primary_10_1016_j_pnucene_2019_03_025
elsevier_sciencedirect_doi_10_1016_j_pnucene_2019_03_025
ProviderPackageCode CITATION
AAYXX
PublicationCentury 2000
PublicationDate August 2019
2019-08-00
20190801
PublicationDateYYYYMMDD 2019-08-01
PublicationDate_xml – month: 08
  year: 2019
  text: August 2019
PublicationDecade 2010
PublicationPlace Oxford
PublicationPlace_xml – name: Oxford
PublicationTitle Progress in nuclear energy (New series)
PublicationYear 2019
Publisher Elsevier Ltd
Elsevier BV
Publisher_xml – name: Elsevier Ltd
– name: Elsevier BV
References Crepeau, Reese, Mcllroy, Lords (bib2) 1998; 16
Springman (bib11) August 2013
ASTM (bib1) 2016
Hambley (bib5) September 2013
Lords, Windes, Crepeau, Sidwell (bib7) May 1996
Rodrigo, Therrien, Surette (bib10) 2005
Large, Sindelar (bib6) Oct. 1999
Nuclear Decommissioning Authority (bib8) Jun. 2012
Goode, Harbottle, Hanson (bib4) 2018; 109
Pajunen (bib9) Dec. 1997
Goode, Harbottle, Hanson (bib3) 2017
Goode (10.1016/j.pnucene.2019.03.025_bib4) 2018; 109
Pajunen (10.1016/j.pnucene.2019.03.025_bib9) 1997
Crepeau (10.1016/j.pnucene.2019.03.025_bib2) 1998; 16
Rodrigo (10.1016/j.pnucene.2019.03.025_bib10) 2005
Large (10.1016/j.pnucene.2019.03.025_bib6) 1999
Goode (10.1016/j.pnucene.2019.03.025_bib3) 2017
Springman (10.1016/j.pnucene.2019.03.025_bib11) 2013
Hambley (10.1016/j.pnucene.2019.03.025_bib5) 2013
Lords (10.1016/j.pnucene.2019.03.025_bib7) 1996
ASTM (10.1016/j.pnucene.2019.03.025_bib1) 2016
Nuclear Decommissioning Authority (10.1016/j.pnucene.2019.03.025_bib8)
References_xml – year: Dec. 1997
  ident: bib9
  article-title: Cold vacuum drying residual free water test description
  publication-title: Tech. Rep. HNF–1851
– volume: 109
  start-page: 145
  year: 2018
  end-page: 158
  ident: bib4
  article-title: Vacuum drying of advanced gas reactor fuel
  publication-title: Prog. Nucl. Energy
– year: Oct. 1999
  ident: bib6
  article-title: Review of drying methods for spent nuclear fuel
  publication-title: Tech. Rep. WSRC-TR-97-0075, Savannah River Site (US), Aiken, SC 29808
– volume: 16
  start-page: 545
  year: 1998
  end-page: 560
  ident: bib2
  article-title: Drying of mock spent nuclear fuel elements
  publication-title: Dry. Technol.
– year: 2005
  ident: bib10
  article-title: Low-temperature, vacuum-assisted drying of degraded spent nuclear fuel
  publication-title: Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities Current Practices and Future Needs
– year: 2017
  ident: bib3
  article-title: Drying simulated advanced gas reactor fuel: proving the concept
  publication-title: Proceedings of WM 2017, Pheonix, Arizona
– year: Jun. 2012
  ident: bib8
  article-title: Oxide fuels - preferred option - publications - GOV.UK, tech. Rep. SMS/TS/C2-OF/001/preferred option
– year: September 2013
  ident: bib5
  article-title: Technical basis for extending storage of AGR fuel
  publication-title: GLOBAL 2013, Salt Lake City
– year: 2016
  ident: bib1
  article-title: Guide for drying behavior of spent nuclear fuel
  publication-title: Tech. Rep. C-1553-16
– year: May 1996
  ident: bib7
  article-title: Drying studies for corroded doe aluminum plate fuels
  publication-title: Tech. Rep. INEL–96/00134; CONF-960804–29
– year: August 2013
  ident: bib11
  article-title: Forced Gas Dehydration (FGD) System for Drying Nuclear Fuel and Waste Packages, 17th Packaging and Transportation of Radioactive Materials Symposium
– year: 1997
  ident: 10.1016/j.pnucene.2019.03.025_bib9
  article-title: Cold vacuum drying residual free water test description
– year: 1996
  ident: 10.1016/j.pnucene.2019.03.025_bib7
  article-title: Drying studies for corroded doe aluminum plate fuels
– volume: 16
  start-page: 545
  issue: 3–5
  year: 1998
  ident: 10.1016/j.pnucene.2019.03.025_bib2
  article-title: Drying of mock spent nuclear fuel elements
  publication-title: Dry. Technol.
  doi: 10.1080/07373939808917423
– year: 2016
  ident: 10.1016/j.pnucene.2019.03.025_bib1
  article-title: Guide for drying behavior of spent nuclear fuel
– year: 2017
  ident: 10.1016/j.pnucene.2019.03.025_bib3
  article-title: Drying simulated advanced gas reactor fuel: proving the concept
– year: 2013
  ident: 10.1016/j.pnucene.2019.03.025_bib5
  article-title: Technical basis for extending storage of AGR fuel
– ident: 10.1016/j.pnucene.2019.03.025_bib8
– year: 2005
  ident: 10.1016/j.pnucene.2019.03.025_bib10
  article-title: Low-temperature, vacuum-assisted drying of degraded spent nuclear fuel
– volume: 109
  start-page: 145
  year: 2018
  ident: 10.1016/j.pnucene.2019.03.025_bib4
  article-title: Vacuum drying of advanced gas reactor fuel
  publication-title: Prog. Nucl. Energy
  doi: 10.1016/j.pnucene.2018.07.011
– year: 2013
  ident: 10.1016/j.pnucene.2019.03.025_bib11
– year: 1999
  ident: 10.1016/j.pnucene.2019.03.025_bib6
  article-title: Review of drying methods for spent nuclear fuel
SSID ssj0017155
ssib019626759
Score 2.2131128
Snippet A drying rig has been constructed to allow detailed comparison of both vacuum drying and flowed gas drying of spent nuclear fuels in response to the upcoming...
SourceID proquest
crossref
elsevier
SourceType Aggregation Database
Enrichment Source
Index Database
Publisher
StartPage 120
SubjectTerms AGR
Cracks
Dry storage
Drying
Drying agents
Energy consumption
Gas cooled reactors
Nuclear fuel
Nuclear fuels
Pinholes
Reprocessing
Spent nuclear fuels
Stainless steel
Stainless steels
Stress corrosion cracking
Title A benchtop comparison of drying methods relevant to failed spent nuclear fuel
URI https://dx.doi.org/10.1016/j.pnucene.2019.03.025
https://www.proquest.com/docview/2250584450
Volume 115
hasFullText 1
inHoldings 1
isFullTextHit
isPrint
link http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwnV1La8JAEB58XNpD6ZPaWtlDrzGvXd0cRSq2RU8VvC3JJqGKxKDx2t_eGbOxDwpCjwnMkny7O_NtMvMNwCMV5YnY0ZZIkb7heSOwpI48K9aSB_TJSWuqd55Me-MZf5mLeQ2GVS0MpVUa31_69L23Nndsg6adLxY2pSUFbkBy4r5DXxvq0PQw2ssGNAfPr-Pp4WdC3xUmkzGwyOCrkMdedvMMIcxIMNMt5U6pafbfIeqXs95HoNE5nBnqyAbl011ALcku4fSboOAVTAYswld4L9Y504cOg2ydsnhD9UysbBi9ZdQqBTl0wYo1S0P0DDHb5hh_WEb6xuGGpbtkdQ2z0dPbcGyZhgmW9v1-YQmNEPdiV-95XJKkbopbth8FfcFdGUdS-8g3UolRS8ZeGPm9JCKBs9BBEuTy2L-BRrbOkltgSEvw4Icb2gtDjpQl8gX3Qhw0EDINPN0CXmGktFETp6YWK1WljS2VgVYRtMrxFULbgu7BLC_lNI4ZyGoC1I91odDlHzNtVxOmzMbcKo8on-RcOHf_H_keTuiqzANsQ6PY7JIH5CZF1IF698PtmBX4CayI4io
linkProvider Elsevier
linkToHtml http://utb.summon.serialssolutions.com/2.0.0/link/0/eLvHCXMwnV1Lb4JAEJ5YPbQ9NH2mtrbdQ68oj0WXozE1Wh8nTbxtYIFUY4Ao_v_OyGIfaWLSK2Q28O3uzLcw8w3AKxXluaGpDDdG-obnDc8QKrCNUAnu0ScnpajeeTJtD-b8feEuKtAra2EorVL7_sKn7721vtLSaLay5bJFaUme5ZGcuGPS14YTqHFqal2FWnc4GkwPPxM6lqszGT2DDL4KeVqrZpYghAkJZlqF3Ck1zf47RP1y1vsI1L-EC00dWbd4uiuoRMk1nH8TFLyBSZcF-AofeZoxdegwyNKYhRuqZ2JFw-gto1YpyKFzlqcs9tEzhGybYfxhCekb-xsW76L1Lcz7b7PewNANEwzlOJ3ccBVC3A4ttedxURRbMW7ZTuB1EBcRBkI5yDdigVFLhLYfOO0oIIEz30QSZPHQuYNqkibRPTCkJXjwww1t-z5HyhI4Lrd9HNRzRezZqg68xEgqrSZOTS3WskwbW0kNrSRopelIhLYOzYNZVshpHDMQ5QTIH-tCoss_ZtooJ0zqjbmVNlE-wblrPvx_5Bc4HcwmYzkeTkePcEZ3ipzABlTzzS56Qp6SB896HX4CAxLkEA
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%3Ajournal&rft.genre=article&rft.atitle=A+benchtop+comparison+of+drying+methods+relevant+to+failed+spent+nuclear+fuel&rft.jtitle=Progress+in+nuclear+energy+%28New+series%29&rft.au=Goode%2C+James+B.&rft.au=Hambley%2C+David+I.&rft.au=Hanson%2C+Bruce+C.&rft.date=2019-08-01&rft.pub=Elsevier+Ltd&rft.issn=0149-1970&rft.volume=115&rft.spage=120&rft.epage=125&rft_id=info:doi/10.1016%2Fj.pnucene.2019.03.025&rft.externalDocID=S0149197019300903
thumbnail_l http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/lc.gif&issn=0149-1970&client=summon
thumbnail_m http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/mc.gif&issn=0149-1970&client=summon
thumbnail_s http://covers-cdn.summon.serialssolutions.com/index.aspx?isbn=/sc.gif&issn=0149-1970&client=summon