Explore: Fuel Burnup (nuclear Engineering)
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AI-Generated Overview About “fuel-burnup-%28nuclear-engineering%29”:
Books Results
Source: The Open Library
The Open Library Search Results
Search results from The Open Library
1Scientific Issues in Fuel Behavior: A Report by an Nea Nuclear Science Committee Task Force
By Nea
“Scientific Issues in Fuel Behavior: A Report by an Nea Nuclear Science Committee Task Force” Metadata:
- Title: ➤ Scientific Issues in Fuel Behavior: A Report by an Nea Nuclear Science Committee Task Force
- Author: Nea
- Language: English
- Number of Pages: Median: 83
- Publisher: ➤ Organization for Economic - OECD Publication and Information Centre, distributor] - Nuclear Energy Agency, Organisation for Economic Co-operation and Development
- Publish Date: 1995
- Publish Location: ➤ Paris, France - [Washington, D.C
“Scientific Issues in Fuel Behavior: A Report by an Nea Nuclear Science Committee Task Force” Subjects and Themes:
- Subjects: Nuclear fuels - Models - Nuclear fuel elements - Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL915640M - OL9127174M
- Online Computer Library Center (OCLC) ID: 32720268
- Library of Congress Control Number (LCCN): 95211973
- All ISBNs: 9789264144200 - 926414420X
Access and General Info:
- First Year Published: 1995
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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2Water reactor fuel extended burnup study
By International Atomic Energy Agency
“Water reactor fuel extended burnup study” Metadata:
- Title: ➤ Water reactor fuel extended burnup study
- Author: ➤ International Atomic Energy Agency
- Language: English
- Number of Pages: Median: 60
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 1992 - 1993
- Publish Location: Vienna
“Water reactor fuel extended burnup study” Subjects and Themes:
- Subjects: Nuclear fuels - Water cooled reactors - Nuclear reactors - Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL1530127M - OL12857727M
- Online Computer Library Center (OCLC) ID: 27313931
- Library of Congress Control Number (LCCN): 93222171
- All ISBNs: 9789201039927 - 9201039921
Access and General Info:
- First Year Published: 1992
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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3Alternative fuel cycle PWR models for the ORIGEN computer code
By A. G Croff
“Alternative fuel cycle PWR models for the ORIGEN computer code” Metadata:
- Title: ➤ Alternative fuel cycle PWR models for the ORIGEN computer code
- Author: A. G Croff
- Language: English
- Number of Pages: Median: 49
- Publisher: ➤ Dept of Energy, Oak Ridge National Laboratory - for sale by the National Technical Information Service]
- Publish Date: 1980
- Publish Location: ➤ [Springfield, Va - Oak Ridge, Tenn
“Alternative fuel cycle PWR models for the ORIGEN computer code” Subjects and Themes:
- Subjects: ➤ Computer programs - Fuel burnup (Nuclear engineering) - Pressurized water reactors - Isotope separation
Edition Identifiers:
- The Open Library ID: OL14881943M
Access and General Info:
- First Year Published: 1980
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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4Alternative fuel cycle PWR models for the ORIGEN computer code
By A. G. Croff
“Alternative fuel cycle PWR models for the ORIGEN computer code” Metadata:
- Title: ➤ Alternative fuel cycle PWR models for the ORIGEN computer code
- Author: A. G. Croff
- Language: English
- Number of Pages: Median: 49
- Publisher: ➤ for sale by the National Technical Information Service] - Dept of Energy, Oak Ridge National Laboratory
- Publish Date: 1980
- Publish Location: ➤ Oak Ridge, Tenn - [Springfield, Va
“Alternative fuel cycle PWR models for the ORIGEN computer code” Subjects and Themes:
- Subjects: ➤ Computer programs - Fuel burnup (Nuclear engineering) - Pressurized water reactors - Isotope separation
Edition Identifiers:
- The Open Library ID: OL17650915M
Access and General Info:
- First Year Published: 1980
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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5Assessment of reactivity margins and loading curves of for PWR burnup-credit cask designs
By J. C. Wagner
“Assessment of reactivity margins and loading curves of for PWR burnup-credit cask designs” Metadata:
- Title: ➤ Assessment of reactivity margins and loading curves of for PWR burnup-credit cask designs
- Author: J. C. Wagner
- Language: English
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2003
- Publish Location: Washington, DC
“Assessment of reactivity margins and loading curves of for PWR burnup-credit cask designs” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Spent reactor fuels - Storage
- Places: United States
Edition Identifiers:
- The Open Library ID: OL16055707M
Access and General Info:
- First Year Published: 2003
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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6Computational benchmark for estimation of reactivity margin from fission products and minor actinides in PWR burnup credit
By J. C. Wagner
“Computational benchmark for estimation of reactivity margin from fission products and minor actinides in PWR burnup credit” Metadata:
- Title: ➤ Computational benchmark for estimation of reactivity margin from fission products and minor actinides in PWR burnup credit
- Author: J. C. Wagner
- Language: English
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, Office Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Computational benchmark for estimation of reactivity margin from fission products and minor actinides in PWR burnup credit” Subjects and Themes:
- Subjects: ➤ Actinide elements - Fission products - Fuel burnup (Nuclear engineering) - Pressurized water reactors - Reactivity - Standards
Edition Identifiers:
- The Open Library ID: OL16032364M
- Online Computer Library Center (OCLC) ID: 52912926
- All ISBNs: 9780160665516 - 0160665515
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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7Parametric study of the effect of burnable poison rods for PWR burnup credit
By J. C. Wagner
“Parametric study of the effect of burnable poison rods for PWR burnup credit” Metadata:
- Title: ➤ Parametric study of the effect of burnable poison rods for PWR burnup credit
- Author: J. C. Wagner
- Language: English
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2002
- Publish Location: Washington, DC
“Parametric study of the effect of burnable poison rods for PWR burnup credit” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Nuclear fuel rods - Pressurized water reactors - Steam power plants
Edition Identifiers:
- The Open Library ID: OL16034277M
- Online Computer Library Center (OCLC) ID: 52906650
- All ISBNs: 9780160671555 - 0160671558
Access and General Info:
- First Year Published: 2002
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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8Recommendations for addressing axial burnup in PWR burnup credit analyses
By J. C. Wagner
“Recommendations for addressing axial burnup in PWR burnup credit analyses” Metadata:
- Title: ➤ Recommendations for addressing axial burnup in PWR burnup credit analyses
- Author: J. C. Wagner
- Language: English
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, U.S. Nuclear Regulatory Commission
- Publish Date: 2003
- Publish Location: Washington, DC
“Recommendations for addressing axial burnup in PWR burnup credit analyses” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Spent reactor fuels - Storage
- Places: United States
Edition Identifiers:
- The Open Library ID: OL16055709M
Access and General Info:
- First Year Published: 2003
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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9Recommendations on the credit for cooling time in PWR burnup credit analyses
By J. C. Wagner
“Recommendations on the credit for cooling time in PWR burnup credit analyses” Metadata:
- Title: ➤ Recommendations on the credit for cooling time in PWR burnup credit analyses
- Author: J. C. Wagner
- Language: English
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2003
- Publish Location: Washington, DC
“Recommendations on the credit for cooling time in PWR burnup credit analyses” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Spent reactor fuels - Storage
- Places: United States
Edition Identifiers:
- The Open Library ID: OL16054267M
Access and General Info:
- First Year Published: 2003
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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10Data base on the behavior of high burnup fuel rods with Zr-1% Nb cladding and UO2 fuel (VVER Type) under reactivity accident conditions
By L. A. Yegorova
“Data base on the behavior of high burnup fuel rods with Zr-1% Nb cladding and UO2 fuel (VVER Type) under reactivity accident conditions” Metadata:
- Title: ➤ Data base on the behavior of high burnup fuel rods with Zr-1% Nb cladding and UO2 fuel (VVER Type) under reactivity accident conditions
- Author: L. A. Yegorova
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 1999
- Publish Location: Washington, D.C
“Data base on the behavior of high burnup fuel rods with Zr-1% Nb cladding and UO2 fuel (VVER Type) under reactivity accident conditions” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Nuclear fuel rods - Testing
Edition Identifiers:
Access and General Info:
- First Year Published: 1999
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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11Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity-initiated accident conditions
By L. A. Yegorova
“Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity-initiated accident conditions” Metadata:
- Title: ➤ Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity-initiated accident conditions
- Author: L. A. Yegorova
- Language: English
- Publisher: ➤ Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2006
- Publish Location: Washington, DC
“Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity-initiated accident conditions” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Nuclear fuels - Nuclear reactors - Reactivity
Edition Identifiers:
- The Open Library ID: OL53756764M
- Online Computer Library Center (OCLC) ID: 827565244
Access and General Info:
- First Year Published: 2006
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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12Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding
By A. Shestopalov, K. Lioutov and L. Yegorova
“Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding” Metadata:
- Title: ➤ Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding
- Authors: A. ShestopalovK. LioutovL. Yegorova
- Language: English
- Number of Pages: Median: 51
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 2003
- Publish Location: Washington, D.C
“Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding” Subjects and Themes:
- Subjects: Nuclear fuel claddings - Niobium-zirconium alloys - Nuclear fuel rods - Safety measures - Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL53143912M
- Online Computer Library Center (OCLC) ID: 54086283
Access and General Info:
- First Year Published: 2003
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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13Review of information for spent nuclear fuel burnup confirmation
By B. B. Bevard
“Review of information for spent nuclear fuel burnup confirmation” Metadata:
- Title: ➤ Review of information for spent nuclear fuel burnup confirmation
- Author: B. B. Bevard
- Language: English
- Number of Pages: Median: 60
- Publisher: ➤ U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2009
- Publish Location: Washington, DC
“Review of information for spent nuclear fuel burnup confirmation” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Spent reactor fuels
- Places: United States
Edition Identifiers:
- The Open Library ID: OL30765072M
- Online Computer Library Center (OCLC) ID: 631265341
- Library of Congress Control Number (LCCN): 2009526130
Access and General Info:
- First Year Published: 2009
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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14Analysis of experimental data for high burnup PWR spent fuel isotopic validation--Calvert Cliffs, Takahama, and Three Mile Island reactors
“Analysis of experimental data for high burnup PWR spent fuel isotopic validation--Calvert Cliffs, Takahama, and Three Mile Island reactors” Metadata:
- Title: ➤ Analysis of experimental data for high burnup PWR spent fuel isotopic validation--Calvert Cliffs, Takahama, and Three Mile Island reactors
- Language: English
- Publisher: ➤ United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2010
- Publish Location: Washington, DC
“Analysis of experimental data for high burnup PWR spent fuel isotopic validation--Calvert Cliffs, Takahama, and Three Mile Island reactors” Subjects and Themes:
- Subjects: ➤ Isotope dilution analysis - Calvert Cliffs Nuclear Power Plant (Md.) - Fuel burnup (Nuclear engineering) - Nuclear facilities - Pressurized water reactors - Three Mile Island Nuclear Power Plant (Pa.)
- Places: Pennsylvania - Japan - Maryland - Calvert Cliffs - Fukui-ken
Edition Identifiers:
- The Open Library ID: OL30765201M
- Library of Congress Control Number (LCCN): 2009526573
Access and General Info:
- First Year Published: 2010
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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15Ot︠s︡enka vozmozhnykh sot︠s︡ialʹno-ėkonomicheskikh posledstviĭ razmeshchenii︠a︡ v Tomskoĭ oblasti zavoda po proizvodstvu MOKS-topliva
By A. V. Toropov
“Ot︠s︡enka vozmozhnykh sot︠s︡ialʹno-ėkonomicheskikh posledstviĭ razmeshchenii︠a︡ v Tomskoĭ oblasti zavoda po proizvodstvu MOKS-topliva” Metadata:
- Title: ➤ Ot︠s︡enka vozmozhnykh sot︠s︡ialʹno-ėkonomicheskikh posledstviĭ razmeshchenii︠a︡ v Tomskoĭ oblasti zavoda po proizvodstvu MOKS-topliva
- Author: A. V. Toropov
- Language: rus
- Number of Pages: Median: 35
- Publisher: Izd-vo "Delʹtaplan"
- Publish Date: 2005
- Publish Location: Tomsk
“Ot︠s︡enka vozmozhnykh sot︠s︡ialʹno-ėkonomicheskikh posledstviĭ razmeshchenii︠a︡ v Tomskoĭ oblasti zavoda po proizvodstvu MOKS-topliva” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Mixed oxide fuels (Nuclear engineering)
- Places: Russia (Federation) - Tomskai︠a︡ oblastʹ
Edition Identifiers:
- The Open Library ID: OL30459621M
- Library of Congress Control Number (LCCN): 2010417868
Access and General Info:
- First Year Published: 2005
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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16Burn-up determination of irradiated thoria samples by isotope dilution-thermal ionisation mass spectrometry
By S. K. Aggarwal
“Burn-up determination of irradiated thoria samples by isotope dilution-thermal ionisation mass spectrometry” Metadata:
- Title: ➤ Burn-up determination of irradiated thoria samples by isotope dilution-thermal ionisation mass spectrometry
- Author: S. K. Aggarwal
- Language: English
- Number of Pages: Median: 19
- Publisher: Bhabha Atomic Research Centre
- Publish Date: 2010
- Publish Location: Mumbai
“Burn-up determination of irradiated thoria samples by isotope dilution-thermal ionisation mass spectrometry” Subjects and Themes:
Edition Identifiers:
- The Open Library ID: OL30632158M
- Library of Congress Control Number (LCCN): 2011321222
Access and General Info:
- First Year Published: 2010
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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17Termoidraulica dei fluidi bifase
By CNEN (Agency : Italy)
“Termoidraulica dei fluidi bifase” Metadata:
- Title: ➤ Termoidraulica dei fluidi bifase
- Author: CNEN (Agency : Italy)
- Language: ita
- Number of Pages: Median: 285
- Publisher: ➤ Comitato nazionale energia nucleare
- Publish Date: 1973
- Publish Location: Roma
“Termoidraulica dei fluidi bifase” Subjects and Themes:
- Subjects: Congresses - Fluid dynamics - Two-phase flow - Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL4667323M
- Library of Congress Control Number (LCCN): 77557877
Access and General Info:
- First Year Published: 1973
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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18The Environmental consequences of higher fuel burn-up
“The Environmental consequences of higher fuel burn-up” Metadata:
- Title: ➤ The Environmental consequences of higher fuel burn-up
- Language: English
- Publisher: The Forum
- Publish Date: 1985
- Publish Location: ➤ Bethesda, MD (7101 Wisconsin Ave., Bethesda 20814-4805)
“The Environmental consequences of higher fuel burn-up” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Environmental aspects - Environmental impact analysis - Envirosphere Company
Edition Identifiers:
- The Open Library ID: OL2626060M
- Library of Congress Control Number (LCCN): 85194939
Access and General Info:
- First Year Published: 1985
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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19Determination of burn-up of irradiated PHWR fuel samples from KAPS-1 by mass spectrometry
By S. K. Aggarwal
“Determination of burn-up of irradiated PHWR fuel samples from KAPS-1 by mass spectrometry” Metadata:
- Title: ➤ Determination of burn-up of irradiated PHWR fuel samples from KAPS-1 by mass spectrometry
- Author: S. K. Aggarwal
- Language: English
- Number of Pages: Median: 43
- Publisher: Bhabha Atomic Research Centre
- Publish Date: 2007
- Publish Location: Mumbai
“Determination of burn-up of irradiated PHWR fuel samples from KAPS-1 by mass spectrometry” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Pressurized water reactors - Mass spectrometry
- Places: India
Edition Identifiers:
- The Open Library ID: OL22503908M
- Library of Congress Control Number (LCCN): 2008331525
Access and General Info:
- First Year Published: 2007
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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20Proceedings of the 24th NSRR Technical Review Meeting
By Japan) NSRR Technical Review Meeting (24th 2000 Tokyo
“Proceedings of the 24th NSRR Technical Review Meeting” Metadata:
- Title: ➤ Proceedings of the 24th NSRR Technical Review Meeting
- Author: ➤ Japan) NSRR Technical Review Meeting (24th 2000 Tokyo
- Language: English
- Number of Pages: Median: 303
- Publisher: ➤ Japan Atomic Energy Research Institute
- Publish Date: 2001
- Publish Location: Tokai-mura, Ibaraki-ken, Japan
“Proceedings of the 24th NSRR Technical Review Meeting” Subjects and Themes:
- Subjects: ➤ Nuclear fuels - Congresses - Safety measures - Light water reactors - Mixed oxide fuels (Nuclear engineering) - Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL31632037M
- Library of Congress Control Number (LCCN): 2004472184
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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21FRAPCON-3
“FRAPCON-3” Metadata:
- Title: FRAPCON-3
- Language: English
- Publisher: The Commission
- Publish Date: 1997
- Publish Location: Wasington, DC
“FRAPCON-3” Subjects and Themes:
- Subjects: ➤ Nuclear fuel rods - Nuclear fuel claddings - Data processing - Fuel burnup (Nuclear engineering) - Mathematical models - Computer-aided engineering
Edition Identifiers:
Access and General Info:
- First Year Published: 1997
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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22Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel
By B. E. Boyack
“Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel” Metadata:
- Title: ➤ Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel
- Author: B. E. Boyack
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2001
- Publish Location: Washington, D.C
“Phenomenon identification and ranking tables (PIRTs) for loss-of-coolant accidents in pressurized and boiling water reactors containing high burnup fuel” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Forecasting - Accidents - Boiling water reactors - Pressurized water reactors
Edition Identifiers:
- The Open Library ID: OL18172463M
- Online Computer Library Center (OCLC) ID: 51552722
- All ISBNs: 9780160665813 - 0160665817
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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23Study of the effect of integral burnable absorbers for PWR burnup credit
By U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
“Study of the effect of integral burnable absorbers for PWR burnup credit” Metadata:
- Title: ➤ Study of the effect of integral burnable absorbers for PWR burnup credit
- Author: ➤ U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2001
- Publish Location: Washington, DC
“Study of the effect of integral burnable absorbers for PWR burnup credit” Subjects and Themes:
- Subjects: ➤ Fuel - Fuel burnup (Nuclear engineering) - Pressurized water reactors - Burnable poisons
Edition Identifiers:
- The Open Library ID: OL16034275M
- Online Computer Library Center (OCLC) ID: 53025479
- All ISBNs: 016067154X - 9780160671548
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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24FRAPCON-3
By D. D. Lanning
“FRAPCON-3” Metadata:
- Title: FRAPCON-3
- Author: D. D. Lanning
- Language: English
- Publisher: ➤ Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 1997
- Publish Location: Washington, DC
“FRAPCON-3” Subjects and Themes:
- Subjects: ➤ Nuclear fuel claddings - Computer-aided engineering - Data processing - Nuclear fuel rods - Oxidation - Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL17580393M
- Online Computer Library Center (OCLC) ID: 40220160
Access and General Info:
- First Year Published: 1997
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
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25Behaviour of Bruce NGS-A fuel irradiated to a burnup of ̃ 500 MWh/kgU
By M. R. Floyd
“Behaviour of Bruce NGS-A fuel irradiated to a burnup of ̃ 500 MWh/kgU” Metadata:
- Title: ➤ Behaviour of Bruce NGS-A fuel irradiated to a burnup of ̃ 500 MWh/kgU
- Author: M. R. Floyd
- Language: English
- Number of Pages: Median: 16
- Publisher: ➤ Fuel Materials Branch, Chalk River Laboratories
- Publish Date: 1992
- Publish Location: Chalk River, Ont
“Behaviour of Bruce NGS-A fuel irradiated to a burnup of ̃ 500 MWh/kgU” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL17378787M
- All ISBNs: 9780660147857 - 0660147858
Access and General Info:
- First Year Published: 1992
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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26Environmental effects of extending fuel burnup above 60 Gwd/MTU
By J. V. Ramsdell
“Environmental effects of extending fuel burnup above 60 Gwd/MTU” Metadata:
- Title: ➤ Environmental effects of extending fuel burnup above 60 Gwd/MTU
- Author: J. V. Ramsdell
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Environmental effects of extending fuel burnup above 60 Gwd/MTU” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Environmental aspects - Nuclear fuel rods
Edition Identifiers:
- The Open Library ID: OL17600359M
- Online Computer Library Center (OCLC) ID: 46458814
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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27Extension of fuel burnup in light water reactors by using a strict in-out refueling scheme
By Julian Yu-liang Yen
“Extension of fuel burnup in light water reactors by using a strict in-out refueling scheme” Metadata:
- Title: ➤ Extension of fuel burnup in light water reactors by using a strict in-out refueling scheme
- Author: Julian Yu-liang Yen
- Language: English
- Number of Pages: Median: 200
- Publish Date: 1982
“Extension of fuel burnup in light water reactors by using a strict in-out refueling scheme” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL15068064M
Access and General Info:
- First Year Published: 1982
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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28Performance of bruce natural UO2 fuel irradiated to extended burnups
By Y. N Zhou
“Performance of bruce natural UO2 fuel irradiated to extended burnups” Metadata:
- Title: ➤ Performance of bruce natural UO2 fuel irradiated to extended burnups
- Author: Y. N Zhou
- Language: English
- Publisher: Chalk River Laboratories
- Publish Date: 1995
- Publish Location: Chalk River, Ont
“Performance of bruce natural UO2 fuel irradiated to extended burnups” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering)
Edition Identifiers:
- The Open Library ID: OL16538783M
- All ISBNs: 9780660162904 - 0660162903
Access and General Info:
- First Year Published: 1995
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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29Analysis of mixed oxide fuel irradiated in EBR-II
By L. D Scott
“Analysis of mixed oxide fuel irradiated in EBR-II” Metadata:
- Title: ➤ Analysis of mixed oxide fuel irradiated in EBR-II
- Author: L. D Scott
- Language: English
- Number of Pages: Median: 13
- Publisher: ➤ for sale by the National Technical Information Service - Dept. of Energy
- Publish Date: 1978
- Publish Location: Springfield, Va - [Washington]
“Analysis of mixed oxide fuel irradiated in EBR-II” Subjects and Themes:
- Subjects: ➤ Oxides - Fuel burnup (Nuclear engineering) - Irradiation
Edition Identifiers:
- The Open Library ID: OL14879951M
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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30Technical specifications for the pool critical assembly
By Oak Ridge National Laboratory. Operations Division.
“Technical specifications for the pool critical assembly” Metadata:
- Title: ➤ Technical specifications for the pool critical assembly
- Author: ➤ Oak Ridge National Laboratory. Operations Division.
- Language: English
- Number of Pages: Median: 35
- Publisher: ➤ Dept. of Energy, [Office of Energy Technology], Oak Ridge National Laboratory - for sale by the National Technical Information Service
- Publish Date: 1978
- Publish Location: ➤ Springfield, Va - Oak Ridge, Tenn
“Technical specifications for the pool critical assembly” Subjects and Themes:
- Subjects: ➤ Nuclear fuels - Fuel burnup (Nuclear engineering) - Nuclear reactors
Edition Identifiers:
- The Open Library ID: OL14881533M
Author's Alternative Names:
"Oak Ridge National Laboratory. Operations Division"Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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31Development of depletion perturbation theory for coupled neutron/nuclide fields
By M. L. Williams
“Development of depletion perturbation theory for coupled neutron/nuclide fields” Metadata:
- Title: ➤ Development of depletion perturbation theory for coupled neutron/nuclide fields
- Author: M. L. Williams
- Language: English
- Number of Pages: Median: 51
- Publisher: ➤ Dept. of Energy, Oak Ridge National Laboratory - for sale by the National Technical Information Service]
- Publish Date: 1978
- Publish Location: ➤ [Springfield, Va - Oak Ridge, Tenn
“Development of depletion perturbation theory for coupled neutron/nuclide fields” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Nuclides - Perturbation (Mathematics)
Edition Identifiers:
- The Open Library ID: OL14881438M
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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32Anticipated transients without scram for light water reactors
By United States. Office of Nuclear Reactor Regulation. Division of Systems Safety
“Anticipated transients without scram for light water reactors” Metadata:
- Title: ➤ Anticipated transients without scram for light water reactors
- Author: ➤ United States. Office of Nuclear Reactor Regulation. Division of Systems Safety
- Language: English
- Publisher: ➤ Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Systems Safety - for sale by the National Technical Information Service
- Publish Date: 1978
- Publish Location: Springfield, Va - Washington
“Anticipated transients without scram for light water reactors” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Safety measures - Nuclear reactors
Edition Identifiers:
- The Open Library ID: OL14947571M
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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33Fuel rod failure as a consequence of departure from nucleate boiling or dryout
By Robert Van Houten
“Fuel rod failure as a consequence of departure from nucleate boiling or dryout” Metadata:
- Title: ➤ Fuel rod failure as a consequence of departure from nucleate boiling or dryout
- Author: Robert Van Houten
- Language: English
- Number of Pages: Median: 23
- Publisher: ➤ Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research - for sale by the National Technical Information Service
- Publish Date: 1979
- Publish Location: Springfield, Va - Washington
“Fuel rod failure as a consequence of departure from nucleate boiling or dryout” Subjects and Themes:
Edition Identifiers:
- The Open Library ID: OL14947692M
Access and General Info:
- First Year Published: 1979
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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34Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system
By Shahab A. Abdul-hamid
“Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system” Metadata:
- Title: ➤ Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system
- Author: Shahab A. Abdul-hamid
- Language: English
- Number of Pages: Median: 143
- Publish Date: 1993
“Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Nuclear reactors
Edition Identifiers:
- The Open Library ID: OL15204466M
Access and General Info:
- First Year Published: 1993
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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35Power excursion analysis for high burnup cores
By David J. Diamond
“Power excursion analysis for high burnup cores” Metadata:
- Title: ➤ Power excursion analysis for high burnup cores
- Author: David J. Diamond
- Language: English
- Publisher: ➤ Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
- Publish Date: 1996
- Publish Location: Washington, DC
“Power excursion analysis for high burnup cores” Subjects and Themes:
- Subjects: ➤ Reliability - Fuel burnup (Nuclear engineering) - Pressurized water reactors - Boiling water reactors
Edition Identifiers:
- The Open Library ID: OL15422275M
Access and General Info:
- First Year Published: 1996
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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36Experimentally determined burnup and spent fuel composition of Yankee Core I
By J. Jedruch
“Experimentally determined burnup and spent fuel composition of Yankee Core I” Metadata:
- Title: ➤ Experimentally determined burnup and spent fuel composition of Yankee Core I
- Author: J. Jedruch
- Language: English
- Number of Pages: Median: 124
- Publisher: ➤ Atomic Power Division, Westinghouse Electric Corp.
- Publish Date: 1965
- Publish Location: Pittsburgh, Pa
“Experimentally determined burnup and spent fuel composition of Yankee Core I” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Spent reactor fuels - Analysis
Edition Identifiers:
- The Open Library ID: OL20250523M
Access and General Info:
- First Year Published: 1965
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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37Limited burnup credit in criticality safety analysis
By I. C. Gauld
“Limited burnup credit in criticality safety analysis” Metadata:
- Title: ➤ Limited burnup credit in criticality safety analysis
- Author: I. C. Gauld
- Language: English
- Number of Pages: Median: 23
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Limited burnup credit in criticality safety analysis” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Reactivity - Nuclear reactors - Criticality (Nuclear engineering) - Safety measures
Edition Identifiers:
- The Open Library ID: OL18157839M
- Online Computer Library Center (OCLC) ID: 52785684
- All ISBNs: 0160615852 - 9780160615856
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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38Anticipated transients without scram for light water reactors
By U.S. Nuclear Regulatory Commission. Division of Systems Safety.
“Anticipated transients without scram for light water reactors” Metadata:
- Title: ➤ Anticipated transients without scram for light water reactors
- Author: ➤ U.S. Nuclear Regulatory Commission. Division of Systems Safety.
- Language: English
- Publisher: ➤ Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Systems Safety - for sale by the National Technical Information Service
- Publish Date: 1978
- Publish Location: Washington - Springfield, Va
“Anticipated transients without scram for light water reactors” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Safety measures - Nuclear reactors
Edition Identifiers:
- The Open Library ID: OL22391959M
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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39Parametric study of the effect of control rods for PWR burnup credit
By C. E. Sanders
“Parametric study of the effect of control rods for PWR burnup credit” Metadata:
- Title: ➤ Parametric study of the effect of control rods for PWR burnup credit
- Author: C. E. Sanders
- Language: English
- Publisher: ➤ Division of System Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2002
- Publish Location: Washington, DC
“Parametric study of the effect of control rods for PWR burnup credit” Subjects and Themes:
- Subjects: ➤ Nuclear fuel rods - Pressurized water reactors - Fuel burnup (Nuclear engineering) - Steam power plants
Edition Identifiers:
- The Open Library ID: OL18174813M
- Online Computer Library Center (OCLC) ID: 52912580
- All ISBNs: 9780160671531 - 0160671531
Access and General Info:
- First Year Published: 2002
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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40STARBUCS
By Oak Ridge National Laboratory
“STARBUCS” Metadata:
- Title: STARBUCS
- Author: Oak Ridge National Laboratory
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2001
- Publish Location: Washington, DC
“STARBUCS” Subjects and Themes:
Edition Identifiers:
- The Open Library ID: OL16032366M
- All ISBNs: 9780160665523 - 0160665523
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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41Advances in applications of burnup credit to enhance spent fuel transportation, storage, reprocessing and disposition
By IAEA
“Advances in applications of burnup credit to enhance spent fuel transportation, storage, reprocessing and disposition” Metadata:
- Title: ➤ Advances in applications of burnup credit to enhance spent fuel transportation, storage, reprocessing and disposition
- Author: IAEA
- Language: English
- Number of Pages: Median: 453
- Publisher: ➤ International Atomic Energy Agency
- Publish Date: 2007
- Publish Location: Vienna
“Advances in applications of burnup credit to enhance spent fuel transportation, storage, reprocessing and disposition” Subjects and Themes:
- Subjects: ➤ Reactor fuel reprocessing - Transportation - Fuel burnup (Nuclear engineering) - Waste disposal - Spent reactor fuels - Storage
Edition Identifiers:
- The Open Library ID: OL16155646M
- All ISBNs: 9789201033079 - 9201033079
Access and General Info:
- First Year Published: 2007
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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42Mechanical fatigue testing of high-burnup fuel for transportation applications
By Jy-An Wang
“Mechanical fatigue testing of high-burnup fuel for transportation applications” Metadata:
- Title: ➤ Mechanical fatigue testing of high-burnup fuel for transportation applications
- Author: Jy-An Wang
- Language: English
- Publisher: ➤ U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research
- Publish Date: 2015
- Publish Location: Washington, DC
“Mechanical fatigue testing of high-burnup fuel for transportation applications” Subjects and Themes:
- Subjects: ➤ Nuclear fuels - Fuel burnup (Nuclear engineering) - Spent reactor fuels - Transportation - Fracture mechanics
Edition Identifiers:
- The Open Library ID: OL27994768M
- Online Computer Library Center (OCLC) ID: 910739036
- Library of Congress Control Number (LCCN): 2014496337
Access and General Info:
- First Year Published: 2015
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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43Implications from the phenomenon identification and ranking tables (PIRTs) and suggested research activities for high burnup fuel
By R. O. Meyer
“Implications from the phenomenon identification and ranking tables (PIRTs) and suggested research activities for high burnup fuel” Metadata:
- Title: ➤ Implications from the phenomenon identification and ranking tables (PIRTs) and suggested research activities for high burnup fuel
- Author: R. O. Meyer
- Language: English
- Number of Pages: Median: 26
- Publisher: ➤ Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
- Publish Date: 2001
- Publish Location: Washington, DC
“Implications from the phenomenon identification and ranking tables (PIRTs) and suggested research activities for high burnup fuel” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Forecasting - Nuclear reactor accidents - Research - Nuclear facilities - Safety measures - Nuclear fuel rods - Nuclear fuel claddings - Nuclear fuel elements - Computer programs - Nuclear accidents
Edition Identifiers:
- The Open Library ID: OL13629619M
- Online Computer Library Center (OCLC) ID: 49731426
Access and General Info:
- First Year Published: 2001
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
Online Access
Downloads Are Not Available:
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44CCB, a two-dimensional diffusion theory continuous cross-section burnup code for fast reactor analysis
By Purdue University. School of Nuclear Engineering.
“CCB, a two-dimensional diffusion theory continuous cross-section burnup code for fast reactor analysis” Metadata:
- Title: ➤ CCB, a two-dimensional diffusion theory continuous cross-section burnup code for fast reactor analysis
- Author: ➤ Purdue University. School of Nuclear Engineering.
- Language: English
- Number of Pages: Median: 200
- Publisher: ➤ Electric Power Research Institute
- Publish Date: 1978
- Publish Location: Palo Alto, Calif
“CCB, a two-dimensional diffusion theory continuous cross-section burnup code for fast reactor analysis” Subjects and Themes:
- Subjects: ➤ Data processing - Fuel burnup (Nuclear engineering) - Liquid metal fast breeder reactors
Edition Identifiers:
- The Open Library ID: OL4765043M
- Library of Congress Control Number (LCCN): 78112348
Access and General Info:
- First Year Published: 1978
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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45Mixed oxide fuel (MOX) exploitation and destruction in power reactors
By Carl E. Walter
“Mixed oxide fuel (MOX) exploitation and destruction in power reactors” Metadata:
- Title: ➤ Mixed oxide fuel (MOX) exploitation and destruction in power reactors
- Author: Carl E. Walter
- Language: English
- Number of Pages: Median: 309
- Publisher: Kluwer Academic
- Publish Date: 1995
- Publish Location: Boston - Dordrecht
“Mixed oxide fuel (MOX) exploitation and destruction in power reactors” Subjects and Themes:
- Subjects: ➤ Radioactive waste disposal - Fuel burnup (Nuclear engineering) - Congresses - Mixed oxide fuels (Nuclear engineering) - Power-plants - Fuel
Edition Identifiers:
- The Open Library ID: OL780525M
- Online Computer Library Center (OCLC) ID: 32349154
- Library of Congress Control Number (LCCN): 95012380
- All ISBNs: 9780792334736 - 0792334736
Access and General Info:
- First Year Published: 1995
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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46Experimental determination of burn-up of mixed-oxide fuels irradiated in PWL, cirus using thermal ionisation mass spectrometry
By S. K. Aggarwal
“Experimental determination of burn-up of mixed-oxide fuels irradiated in PWL, cirus using thermal ionisation mass spectrometry” Metadata:
- Title: ➤ Experimental determination of burn-up of mixed-oxide fuels irradiated in PWL, cirus using thermal ionisation mass spectrometry
- Author: S. K. Aggarwal
- Language: English
- Number of Pages: Median: 19
- Publisher: Bhabha Atomic Research Centre
- Publish Date: 2011
- Publish Location: Mumbai
“Experimental determination of burn-up of mixed-oxide fuels irradiated in PWL, cirus using thermal ionisation mass spectrometry” Subjects and Themes:
- Subjects: ➤ Fuel burnup (Nuclear engineering) - Mixed oxide fuels (Nuclear engineering) - Pressurized water reactors - Mass spectrometry
Edition Identifiers:
- The Open Library ID: OL25206883M
- Library of Congress Control Number (LCCN): 2012323504
Access and General Info:
- First Year Published: 2011
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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47Fission gas behaviour in water reactor fuels
By OECD Nuclear Energy Agency
“Fission gas behaviour in water reactor fuels” Metadata:
- Title: ➤ Fission gas behaviour in water reactor fuels
- Author: OECD Nuclear Energy Agency
- Language: English
- Number of Pages: Median: 559
- Publisher: ➤ Nuclear Energy Agency, Organisation for Economic Co-operation and Development
- Publish Date: 2002
- Publish Location: Paris, France
“Fission gas behaviour in water reactor fuels” Subjects and Themes:
- Subjects: ➤ Nuclear fuels - Fuel burnup (Nuclear engineering) - Congresses - Fission gases
Edition Identifiers:
- The Open Library ID: OL3650711M
- Library of Congress Control Number (LCCN): 2002494268
- All ISBNs: 9789264197152 - 926419715X
Access and General Info:
- First Year Published: 2002
- Is Full Text Available: No
- Is The Book Public: No
- Access Status: No_ebook
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Find Fission gas behaviour in water reactor fuels at online marketplaces:
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