Thermal and Reliability Criteria for Nuclear Fuel Safety.
The book covers basic approaches to the nuclear fuel state of energy reactors in the last stages of the nuclear fuel cycle, these have been developed by the authors based on Ukrainian Nuclear Power Plant (NPP) operational experience.
Saved in:
Superior document: | River Publishers Series in Chemical, Environmental, and Energy Engineering Series |
---|---|
: | |
TeilnehmendeR: | |
Place / Publishing House: | Aalborg : : River Publishers,, 2021. Ã2021. |
Year of Publication: | 2021 |
Edition: | 1st ed. |
Language: | English |
Series: | River Publishers Series in Chemical, Environmental, and Energy Engineering Series
|
Online Access: | |
Physical Description: | 1 online resource (287 pages) |
Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
id |
5006641374 |
---|---|
ctrlnum |
(MiAaPQ)5006641374 (Au-PeEL)EBL6641374 (OCoLC)1257076118 |
collection |
bib_alma |
record_format |
marc |
spelling |
Maksymov, Maksym. Thermal and Reliability Criteria for Nuclear Fuel Safety. 1st ed. Aalborg : River Publishers, 2021. Ã2021. 1 online resource (287 pages) text txt rdacontent computer c rdamedia online resource cr rdacarrier River Publishers Series in Chemical, Environmental, and Energy Engineering Series Cover -- Half Title -- Series Page -- Title Page -- Copyright Page -- Table of Contents -- Afterword -- Preface -- List of Figures -- List of Tables -- List of Abbreviations -- 1: Physical Safety Basis of WWER Nuclear Fuel -- 1.1 Fuel Burn-Up as a Nuclear Safety Criterion -- 1.2 Influence of the Reactor Operating Mode on the Efficiency of WWER-1000 Fuel Cycles -- 1.3 Design Constraints and Engineer Suitable Coefficients When Designing and Operating WWER Fuel Loads -- 1.4 Criteria and Methods of Nuclear Fuel Safety Evaluation Under Operation -- 2: Modern Approaches to the Heat Exchange Modeling in NPP Equipment -- 2.1 Abstract Models -- 2.2 Generalization of the Mathematical Model -- 2.3 Simplified Method of the Numerical Solution of Nonstationary Heat Transfer Problem Through a Flat Wall -- 2.4 Method of Approximate Analytical Solution of a Nonstationary Heat Transfer Problem Through a Flat Wall -- 3: Safety Criteria for WWER-1000 Fuel Assembly When Making a Decision About Its Dry Storage -- 3.1 Variable Modes of NPP Operation -- 3.2 Assessment of Emergency of Fuel Assemblies in Light Water Reactors (LWR) -- 3.3 Qualitative Evaluation of WWER-1000 Fuel Assemblies -- 3.4 Performance Criteria of Fuel Elements -- 4: Effect of Reactor Capacity Cyclic Changes On Energy Accumulation of Irreversible Creep Deformations in Fuel Claddings -- 4.1 Simulation of Technological Parameters of the NPP with WWER-1000 Under Cyclic Loading -- 4.2 Analysis of the Effect of Parameter Variations of Control Programs on the State of Fuel Assemblies During the Cyclic Change of the Reactor Capacity -- 4.3 Uniformity of NPP Energy Release Parameters -- 4.4 Simulation of Fuel Cladding Failure and Axial Offset in the Cyclic Mode of the NPP Operation -- 5: Analysis of WWER 1000 Fuel Cladding Failure. 5.1 Initial Data of the Evaluation Model of the Probability of Fuel Cladding Depressurization -- 5.2 Simulation of Fuel Cladding Reliability -- 5.3 Computational Method of Fuel Cladding Failure -- 5.4 Computational Analyses of Stress-Strain State of the Fuel Cladding -- 6: Thermal Safety Criteria for Dry Storage of Spent Nuclear Fuel -- 6.1 Dry Storage of Spent Nuclear Fuel in Ukraine -- 6.2 Method of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel -- 6.3 Thermal Condition of Containers for Dry Storage of WWER-1000 Spent Nuclear Fuel -- Index -- About the Authors. The book covers basic approaches to the nuclear fuel state of energy reactors in the last stages of the nuclear fuel cycle, these have been developed by the authors based on Ukrainian Nuclear Power Plant (NPP) operational experience. Description based on publisher supplied metadata and other sources. Electronic reproduction. Ann Arbor, Michigan : ProQuest Ebook Central, 2024. Available via World Wide Web. Access may be limited to ProQuest Ebook Central affiliated libraries. Nuclear fuels--Safety measures. Electronic books. Alyokhina, Svitlana. Brunetkin, Oleksandr. Print version: Maksymov, Maksym Thermal and Reliability Criteria for Nuclear Fuel Safety Aalborg : River Publishers,c2021 9788770224017 ProQuest (Firm) https://ebookcentral.proquest.com/lib/oeawat/detail.action?docID=6641374 Click to View |
language |
English |
format |
eBook |
author |
Maksymov, Maksym. |
spellingShingle |
Maksymov, Maksym. Thermal and Reliability Criteria for Nuclear Fuel Safety. River Publishers Series in Chemical, Environmental, and Energy Engineering Series Cover -- Half Title -- Series Page -- Title Page -- Copyright Page -- Table of Contents -- Afterword -- Preface -- List of Figures -- List of Tables -- List of Abbreviations -- 1: Physical Safety Basis of WWER Nuclear Fuel -- 1.1 Fuel Burn-Up as a Nuclear Safety Criterion -- 1.2 Influence of the Reactor Operating Mode on the Efficiency of WWER-1000 Fuel Cycles -- 1.3 Design Constraints and Engineer Suitable Coefficients When Designing and Operating WWER Fuel Loads -- 1.4 Criteria and Methods of Nuclear Fuel Safety Evaluation Under Operation -- 2: Modern Approaches to the Heat Exchange Modeling in NPP Equipment -- 2.1 Abstract Models -- 2.2 Generalization of the Mathematical Model -- 2.3 Simplified Method of the Numerical Solution of Nonstationary Heat Transfer Problem Through a Flat Wall -- 2.4 Method of Approximate Analytical Solution of a Nonstationary Heat Transfer Problem Through a Flat Wall -- 3: Safety Criteria for WWER-1000 Fuel Assembly When Making a Decision About Its Dry Storage -- 3.1 Variable Modes of NPP Operation -- 3.2 Assessment of Emergency of Fuel Assemblies in Light Water Reactors (LWR) -- 3.3 Qualitative Evaluation of WWER-1000 Fuel Assemblies -- 3.4 Performance Criteria of Fuel Elements -- 4: Effect of Reactor Capacity Cyclic Changes On Energy Accumulation of Irreversible Creep Deformations in Fuel Claddings -- 4.1 Simulation of Technological Parameters of the NPP with WWER-1000 Under Cyclic Loading -- 4.2 Analysis of the Effect of Parameter Variations of Control Programs on the State of Fuel Assemblies During the Cyclic Change of the Reactor Capacity -- 4.3 Uniformity of NPP Energy Release Parameters -- 4.4 Simulation of Fuel Cladding Failure and Axial Offset in the Cyclic Mode of the NPP Operation -- 5: Analysis of WWER 1000 Fuel Cladding Failure. 5.1 Initial Data of the Evaluation Model of the Probability of Fuel Cladding Depressurization -- 5.2 Simulation of Fuel Cladding Reliability -- 5.3 Computational Method of Fuel Cladding Failure -- 5.4 Computational Analyses of Stress-Strain State of the Fuel Cladding -- 6: Thermal Safety Criteria for Dry Storage of Spent Nuclear Fuel -- 6.1 Dry Storage of Spent Nuclear Fuel in Ukraine -- 6.2 Method of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel -- 6.3 Thermal Condition of Containers for Dry Storage of WWER-1000 Spent Nuclear Fuel -- Index -- About the Authors. |
author_facet |
Maksymov, Maksym. Alyokhina, Svitlana. Brunetkin, Oleksandr. |
author_variant |
m m mm |
author2 |
Alyokhina, Svitlana. Brunetkin, Oleksandr. |
author2_variant |
s a sa o b ob |
author2_role |
TeilnehmendeR TeilnehmendeR |
author_sort |
Maksymov, Maksym. |
title |
Thermal and Reliability Criteria for Nuclear Fuel Safety. |
title_full |
Thermal and Reliability Criteria for Nuclear Fuel Safety. |
title_fullStr |
Thermal and Reliability Criteria for Nuclear Fuel Safety. |
title_full_unstemmed |
Thermal and Reliability Criteria for Nuclear Fuel Safety. |
title_auth |
Thermal and Reliability Criteria for Nuclear Fuel Safety. |
title_new |
Thermal and Reliability Criteria for Nuclear Fuel Safety. |
title_sort |
thermal and reliability criteria for nuclear fuel safety. |
series |
River Publishers Series in Chemical, Environmental, and Energy Engineering Series |
series2 |
River Publishers Series in Chemical, Environmental, and Energy Engineering Series |
publisher |
River Publishers, |
publishDate |
2021 |
physical |
1 online resource (287 pages) |
edition |
1st ed. |
contents |
Cover -- Half Title -- Series Page -- Title Page -- Copyright Page -- Table of Contents -- Afterword -- Preface -- List of Figures -- List of Tables -- List of Abbreviations -- 1: Physical Safety Basis of WWER Nuclear Fuel -- 1.1 Fuel Burn-Up as a Nuclear Safety Criterion -- 1.2 Influence of the Reactor Operating Mode on the Efficiency of WWER-1000 Fuel Cycles -- 1.3 Design Constraints and Engineer Suitable Coefficients When Designing and Operating WWER Fuel Loads -- 1.4 Criteria and Methods of Nuclear Fuel Safety Evaluation Under Operation -- 2: Modern Approaches to the Heat Exchange Modeling in NPP Equipment -- 2.1 Abstract Models -- 2.2 Generalization of the Mathematical Model -- 2.3 Simplified Method of the Numerical Solution of Nonstationary Heat Transfer Problem Through a Flat Wall -- 2.4 Method of Approximate Analytical Solution of a Nonstationary Heat Transfer Problem Through a Flat Wall -- 3: Safety Criteria for WWER-1000 Fuel Assembly When Making a Decision About Its Dry Storage -- 3.1 Variable Modes of NPP Operation -- 3.2 Assessment of Emergency of Fuel Assemblies in Light Water Reactors (LWR) -- 3.3 Qualitative Evaluation of WWER-1000 Fuel Assemblies -- 3.4 Performance Criteria of Fuel Elements -- 4: Effect of Reactor Capacity Cyclic Changes On Energy Accumulation of Irreversible Creep Deformations in Fuel Claddings -- 4.1 Simulation of Technological Parameters of the NPP with WWER-1000 Under Cyclic Loading -- 4.2 Analysis of the Effect of Parameter Variations of Control Programs on the State of Fuel Assemblies During the Cyclic Change of the Reactor Capacity -- 4.3 Uniformity of NPP Energy Release Parameters -- 4.4 Simulation of Fuel Cladding Failure and Axial Offset in the Cyclic Mode of the NPP Operation -- 5: Analysis of WWER 1000 Fuel Cladding Failure. 5.1 Initial Data of the Evaluation Model of the Probability of Fuel Cladding Depressurization -- 5.2 Simulation of Fuel Cladding Reliability -- 5.3 Computational Method of Fuel Cladding Failure -- 5.4 Computational Analyses of Stress-Strain State of the Fuel Cladding -- 6: Thermal Safety Criteria for Dry Storage of Spent Nuclear Fuel -- 6.1 Dry Storage of Spent Nuclear Fuel in Ukraine -- 6.2 Method of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel -- 6.3 Thermal Condition of Containers for Dry Storage of WWER-1000 Spent Nuclear Fuel -- Index -- About the Authors. |
isbn |
9781000793185 9788770224017 |
callnumber-first |
T - Technology |
callnumber-subject |
TK - Electrical and Nuclear Engineering |
callnumber-label |
TK9360 |
callnumber-sort |
TK 49360 |
genre |
Electronic books. |
genre_facet |
Electronic books. |
url |
https://ebookcentral.proquest.com/lib/oeawat/detail.action?docID=6641374 |
illustrated |
Not Illustrated |
dewey-hundreds |
600 - Technology |
dewey-tens |
620 - Engineering |
dewey-ones |
621 - Applied physics |
dewey-full |
621.48335 |
dewey-sort |
3621.48335 |
dewey-raw |
621.48335 |
dewey-search |
621.48335 |
oclc_num |
1257076118 |
work_keys_str_mv |
AT maksymovmaksym thermalandreliabilitycriteriafornuclearfuelsafety AT alyokhinasvitlana thermalandreliabilitycriteriafornuclearfuelsafety AT brunetkinoleksandr thermalandreliabilitycriteriafornuclearfuelsafety |
status_str |
n |
ids_txt_mv |
(MiAaPQ)5006641374 (Au-PeEL)EBL6641374 (OCoLC)1257076118 |
carrierType_str_mv |
cr |
hierarchy_parent_title |
River Publishers Series in Chemical, Environmental, and Energy Engineering Series |
is_hierarchy_title |
Thermal and Reliability Criteria for Nuclear Fuel Safety. |
container_title |
River Publishers Series in Chemical, Environmental, and Energy Engineering Series |
author2_original_writing_str_mv |
noLinkedField noLinkedField |
marc_error |
Info : Unimarc and ISO-8859-1 translations identical, choosing ISO-8859-1. --- [ 856 : z ] |
_version_ |
1792331059326615552 |
fullrecord |
<?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>04460nam a22004693i 4500</leader><controlfield tag="001">5006641374</controlfield><controlfield tag="003">MiAaPQ</controlfield><controlfield tag="005">20240229073842.0</controlfield><controlfield tag="006">m o d | </controlfield><controlfield tag="007">cr cnu||||||||</controlfield><controlfield tag="008">240229s2021 xx o ||||0 eng d</controlfield><datafield tag="020" ind1=" " ind2=" "><subfield code="a">9781000793185</subfield><subfield code="q">(electronic bk.)</subfield></datafield><datafield tag="020" ind1=" " ind2=" "><subfield code="z">9788770224017</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(MiAaPQ)5006641374</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(Au-PeEL)EBL6641374</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(OCoLC)1257076118</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">MiAaPQ</subfield><subfield code="b">eng</subfield><subfield code="e">rda</subfield><subfield code="e">pn</subfield><subfield code="c">MiAaPQ</subfield><subfield code="d">MiAaPQ</subfield></datafield><datafield tag="050" ind1=" " ind2="4"><subfield code="a">TK9360</subfield></datafield><datafield tag="082" ind1="0" ind2=" "><subfield code="a">621.48335</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Maksymov, Maksym.</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Thermal and Reliability Criteria for Nuclear Fuel Safety.</subfield></datafield><datafield tag="250" ind1=" " ind2=" "><subfield code="a">1st ed.</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="a">Aalborg :</subfield><subfield code="b">River Publishers,</subfield><subfield code="c">2021.</subfield></datafield><datafield tag="264" ind1=" " ind2="4"><subfield code="c">Ã2021.</subfield></datafield><datafield tag="300" ind1=" " ind2=" "><subfield code="a">1 online resource (287 pages)</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">computer</subfield><subfield code="b">c</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">online resource</subfield><subfield code="b">cr</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="490" ind1="1" ind2=" "><subfield code="a">River Publishers Series in Chemical, Environmental, and Energy Engineering Series</subfield></datafield><datafield tag="505" ind1="0" ind2=" "><subfield code="a">Cover -- Half Title -- Series Page -- Title Page -- Copyright Page -- Table of Contents -- Afterword -- Preface -- List of Figures -- List of Tables -- List of Abbreviations -- 1: Physical Safety Basis of WWER Nuclear Fuel -- 1.1 Fuel Burn-Up as a Nuclear Safety Criterion -- 1.2 Influence of the Reactor Operating Mode on the Efficiency of WWER-1000 Fuel Cycles -- 1.3 Design Constraints and Engineer Suitable Coefficients When Designing and Operating WWER Fuel Loads -- 1.4 Criteria and Methods of Nuclear Fuel Safety Evaluation Under Operation -- 2: Modern Approaches to the Heat Exchange Modeling in NPP Equipment -- 2.1 Abstract Models -- 2.2 Generalization of the Mathematical Model -- 2.3 Simplified Method of the Numerical Solution of Nonstationary Heat Transfer Problem Through a Flat Wall -- 2.4 Method of Approximate Analytical Solution of a Nonstationary Heat Transfer Problem Through a Flat Wall -- 3: Safety Criteria for WWER-1000 Fuel Assembly When Making a Decision About Its Dry Storage -- 3.1 Variable Modes of NPP Operation -- 3.2 Assessment of Emergency of Fuel Assemblies in Light Water Reactors (LWR) -- 3.3 Qualitative Evaluation of WWER-1000 Fuel Assemblies -- 3.4 Performance Criteria of Fuel Elements -- 4: Effect of Reactor Capacity Cyclic Changes On Energy Accumulation of Irreversible Creep Deformations in Fuel Claddings -- 4.1 Simulation of Technological Parameters of the NPP with WWER-1000 Under Cyclic Loading -- 4.2 Analysis of the Effect of Parameter Variations of Control Programs on the State of Fuel Assemblies During the Cyclic Change of the Reactor Capacity -- 4.3 Uniformity of NPP Energy Release Parameters -- 4.4 Simulation of Fuel Cladding Failure and Axial Offset in the Cyclic Mode of the NPP Operation -- 5: Analysis of WWER 1000 Fuel Cladding Failure.</subfield></datafield><datafield tag="505" ind1="8" ind2=" "><subfield code="a">5.1 Initial Data of the Evaluation Model of the Probability of Fuel Cladding Depressurization -- 5.2 Simulation of Fuel Cladding Reliability -- 5.3 Computational Method of Fuel Cladding Failure -- 5.4 Computational Analyses of Stress-Strain State of the Fuel Cladding -- 6: Thermal Safety Criteria for Dry Storage of Spent Nuclear Fuel -- 6.1 Dry Storage of Spent Nuclear Fuel in Ukraine -- 6.2 Method of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel -- 6.3 Thermal Condition of Containers for Dry Storage of WWER-1000 Spent Nuclear Fuel -- Index -- About the Authors.</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">The book covers basic approaches to the nuclear fuel state of energy reactors in the last stages of the nuclear fuel cycle, these have been developed by the authors based on Ukrainian Nuclear Power Plant (NPP) operational experience.</subfield></datafield><datafield tag="588" ind1=" " ind2=" "><subfield code="a">Description based on publisher supplied metadata and other sources.</subfield></datafield><datafield tag="590" ind1=" " ind2=" "><subfield code="a">Electronic reproduction. Ann Arbor, Michigan : ProQuest Ebook Central, 2024. Available via World Wide Web. Access may be limited to ProQuest Ebook Central affiliated libraries. </subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Nuclear fuels--Safety measures.</subfield></datafield><datafield tag="655" ind1=" " ind2="4"><subfield code="a">Electronic books.</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Alyokhina, Svitlana.</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Brunetkin, Oleksandr.</subfield></datafield><datafield tag="776" ind1="0" ind2="8"><subfield code="i">Print version:</subfield><subfield code="a">Maksymov, Maksym</subfield><subfield code="t">Thermal and Reliability Criteria for Nuclear Fuel Safety</subfield><subfield code="d">Aalborg : River Publishers,c2021</subfield><subfield code="z">9788770224017</subfield></datafield><datafield tag="797" ind1="2" ind2=" "><subfield code="a">ProQuest (Firm)</subfield></datafield><datafield tag="830" ind1=" " ind2="0"><subfield code="a">River Publishers Series in Chemical, Environmental, and Energy Engineering Series</subfield></datafield><datafield tag="856" ind1="4" ind2="0"><subfield code="u">https://ebookcentral.proquest.com/lib/oeawat/detail.action?docID=6641374</subfield><subfield code="z">Click to View</subfield></datafield></record></collection> |