Current state of research on pressurized water reactor safety / / Jean Couturier, Michel Schwarz.

For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-co...

Full description

Saved in:
Bibliographic Details
Superior document:Science and Technology Series
VerfasserIn:
TeilnehmendeR:
Place / Publishing House:[Place of publication not identified] : : EDP Sciences,, [2018]
©2018
Year of Publication:2018
Edition:1st ed.
Language:English
Series:Science & technology series.
Physical Description:1 online resource (xxxii, 194 pages) :; illustrations.
Tags: Add Tag
No Tags, Be the first to tag this record!
id 993603416804498
ctrlnum (CKB)4340000000258149
(Au-PeEL)EBL5317419
(CaPaEBR)ebr11541885
(OCoLC)1028955613
(DE-B1597)573550
(DE-B1597)9782759821655
(PPN)233399801
(FR-PaCSA)88854836
(MiAaPQ)EBC5317419
(EXLCZ)994340000000258149
collection bib_alma
record_format marc
spelling Couturier, Jean, author.
Current state of research on pressurized water reactor safety / Jean Couturier, Michel Schwarz.
1st ed.
[Place of publication not identified] : EDP Sciences, [2018]
©2018
1 online resource (xxxii, 194 pages) : illustrations.
text txt rdacontent
computer c rdamedia
online resource cr rdacarrier
Science and Technology Series
Description based on print version record.
This eBook is made available Open Access under a CC BY-NC-ND 4.0 license: https://creativecommons.org/licenses/by-nc-nd/4.0 https://www.degruyter.com/dg/page/open-access-policy
For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally. This publication reflects IRSN's desire to keep an enduring record of its results and to share its knowledge.
Frontmatter -- Preface -- The authors -- List of abbreviations -- Foreword -- Contents -- Chapter 1. Introduction -- Chapter 2. Some of the Research Facilities Favored by IRSN in the Field of Nuclear Power Reactor Safety -- Chapter 3. Research on Loss-of-coolant Accidents -- Chapter 4. Research on Reactivity-initiated Accidents -- Chapter 5. Research on Recirculation Cooling under Accident Conditions -- Chapter 6. Research on Spent Fuel Pool Uncovery Accidents -- Chapter 7. Research on Fires -- Chapter 8. Research on Hazards associated to Natural Events -- Chapter 9. Research on Core Melt Accidents -- Chapter 10. Research on the Behavior of Components Important to the Safety of NPPs and More Particularly the Aging of Such Components -- Chapter 11. Research in the Field of Human and Organizational Factors and, More Broadly, in Human and Social Sciences -- Chapter 12. Other Research and Tracks of New Research
Water cooled reactors.
Nuclear reactors Security measures.
Schwarz, Michel, author.
2-7598-2165-X
Science & technology series.
language English
format eBook
author Couturier, Jean,
Schwarz, Michel,
spellingShingle Couturier, Jean,
Schwarz, Michel,
Current state of research on pressurized water reactor safety /
Science and Technology Series
Frontmatter --
Preface --
The authors --
List of abbreviations --
Foreword --
Contents --
Chapter 1. Introduction --
Chapter 2. Some of the Research Facilities Favored by IRSN in the Field of Nuclear Power Reactor Safety --
Chapter 3. Research on Loss-of-coolant Accidents --
Chapter 4. Research on Reactivity-initiated Accidents --
Chapter 5. Research on Recirculation Cooling under Accident Conditions --
Chapter 6. Research on Spent Fuel Pool Uncovery Accidents --
Chapter 7. Research on Fires --
Chapter 8. Research on Hazards associated to Natural Events --
Chapter 9. Research on Core Melt Accidents --
Chapter 10. Research on the Behavior of Components Important to the Safety of NPPs and More Particularly the Aging of Such Components --
Chapter 11. Research in the Field of Human and Organizational Factors and, More Broadly, in Human and Social Sciences --
Chapter 12. Other Research and Tracks of New Research
author_facet Couturier, Jean,
Schwarz, Michel,
Schwarz, Michel,
author_variant j c jc
m s ms
author_role VerfasserIn
VerfasserIn
author2 Schwarz, Michel,
author2_role TeilnehmendeR
author_sort Couturier, Jean,
title Current state of research on pressurized water reactor safety /
title_full Current state of research on pressurized water reactor safety / Jean Couturier, Michel Schwarz.
title_fullStr Current state of research on pressurized water reactor safety / Jean Couturier, Michel Schwarz.
title_full_unstemmed Current state of research on pressurized water reactor safety / Jean Couturier, Michel Schwarz.
title_auth Current state of research on pressurized water reactor safety /
title_alt Frontmatter --
Preface --
The authors --
List of abbreviations --
Foreword --
Contents --
Chapter 1. Introduction --
Chapter 2. Some of the Research Facilities Favored by IRSN in the Field of Nuclear Power Reactor Safety --
Chapter 3. Research on Loss-of-coolant Accidents --
Chapter 4. Research on Reactivity-initiated Accidents --
Chapter 5. Research on Recirculation Cooling under Accident Conditions --
Chapter 6. Research on Spent Fuel Pool Uncovery Accidents --
Chapter 7. Research on Fires --
Chapter 8. Research on Hazards associated to Natural Events --
Chapter 9. Research on Core Melt Accidents --
Chapter 10. Research on the Behavior of Components Important to the Safety of NPPs and More Particularly the Aging of Such Components --
Chapter 11. Research in the Field of Human and Organizational Factors and, More Broadly, in Human and Social Sciences --
Chapter 12. Other Research and Tracks of New Research
title_new Current state of research on pressurized water reactor safety /
title_sort current state of research on pressurized water reactor safety /
series Science and Technology Series
series2 Science and Technology Series
publisher EDP Sciences,
publishDate 2018
physical 1 online resource (xxxii, 194 pages) : illustrations.
edition 1st ed.
contents Frontmatter --
Preface --
The authors --
List of abbreviations --
Foreword --
Contents --
Chapter 1. Introduction --
Chapter 2. Some of the Research Facilities Favored by IRSN in the Field of Nuclear Power Reactor Safety --
Chapter 3. Research on Loss-of-coolant Accidents --
Chapter 4. Research on Reactivity-initiated Accidents --
Chapter 5. Research on Recirculation Cooling under Accident Conditions --
Chapter 6. Research on Spent Fuel Pool Uncovery Accidents --
Chapter 7. Research on Fires --
Chapter 8. Research on Hazards associated to Natural Events --
Chapter 9. Research on Core Melt Accidents --
Chapter 10. Research on the Behavior of Components Important to the Safety of NPPs and More Particularly the Aging of Such Components --
Chapter 11. Research in the Field of Human and Organizational Factors and, More Broadly, in Human and Social Sciences --
Chapter 12. Other Research and Tracks of New Research
isbn 2-7598-2165-X
callnumber-first T - Technology
callnumber-subject TK - Electrical and Nuclear Engineering
callnumber-label TK9203
callnumber-sort TK 49203 W37 C688 42018
illustrated Illustrated
dewey-hundreds 600 - Technology
dewey-tens 620 - Engineering
dewey-ones 621 - Applied physics
dewey-full 621.4831
dewey-sort 3621.4831
dewey-raw 621.4831
dewey-search 621.4831
oclc_num 1028955613
work_keys_str_mv AT couturierjean currentstateofresearchonpressurizedwaterreactorsafety
AT schwarzmichel currentstateofresearchonpressurizedwaterreactorsafety
status_str n
ids_txt_mv (CKB)4340000000258149
(Au-PeEL)EBL5317419
(CaPaEBR)ebr11541885
(OCoLC)1028955613
(DE-B1597)573550
(DE-B1597)9782759821655
(PPN)233399801
(FR-PaCSA)88854836
(MiAaPQ)EBC5317419
(EXLCZ)994340000000258149
carrierType_str_mv cr
hierarchy_parent_title Science and Technology Series
is_hierarchy_title Current state of research on pressurized water reactor safety /
container_title Science and Technology Series
author2_original_writing_str_mv noLinkedField
_version_ 1801431353638518784
fullrecord <?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>03990nam a2200493 i 4500</leader><controlfield tag="001">993603416804498</controlfield><controlfield tag="005">20240506161243.0</controlfield><controlfield tag="006">m o d | </controlfield><controlfield tag="007">cr cnu||||||||</controlfield><controlfield tag="008">180522s2018 xx a o 000 0 eng d</controlfield><datafield tag="024" ind1="7" ind2=" "><subfield code="a">10.1051/978-2-7598-2165-5</subfield><subfield code="2">doi</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(CKB)4340000000258149</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(Au-PeEL)EBL5317419</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(CaPaEBR)ebr11541885</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(OCoLC)1028955613</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-B1597)573550</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-B1597)9782759821655</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(PPN)233399801</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(FR-PaCSA)88854836</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(MiAaPQ)EBC5317419</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(EXLCZ)994340000000258149</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="044" ind1=" " ind2=" "><subfield code="a">fr</subfield><subfield code="c">FR</subfield></datafield><datafield tag="050" ind1=" " ind2="4"><subfield code="a">TK9203.W37</subfield><subfield code="b">.C688 2018</subfield></datafield><datafield tag="072" ind1=" " ind2="7"><subfield code="a">SCI058000</subfield><subfield code="2">bisacsh</subfield></datafield><datafield tag="082" ind1="0" ind2=" "><subfield code="a">621.4831</subfield><subfield code="2">23</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Couturier, Jean,</subfield><subfield code="e">author.</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Current state of research on pressurized water reactor safety /</subfield><subfield code="c">Jean Couturier, Michel Schwarz.</subfield></datafield><datafield tag="250" ind1=" " ind2=" "><subfield code="a">1st ed.</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="a">[Place of publication not identified] :</subfield><subfield code="b">EDP Sciences,</subfield><subfield code="c">[2018]</subfield></datafield><datafield tag="264" ind1=" " ind2="4"><subfield code="c">©2018</subfield></datafield><datafield tag="300" ind1=" " ind2=" "><subfield code="a">1 online resource (xxxii, 194 pages) :</subfield><subfield code="b">illustrations.</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">Science and Technology Series</subfield></datafield><datafield tag="588" ind1=" " ind2=" "><subfield code="a">Description based on print version record.</subfield></datafield><datafield tag="540" ind1=" " ind2=" "><subfield code="a">This eBook is made available Open Access under a CC BY-NC-ND 4.0 license: </subfield><subfield code="u">https://creativecommons.org/licenses/by-nc-nd/4.0 </subfield><subfield code="u">https://www.degruyter.com/dg/page/open-access-policy</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">For more than 40 years, IPSN then IRSN has conducted research and development on nuclear safety, specifically concerning pressurized water reactors, which are the reactor type used in France. This publication reports on the progress of this research and development in each area of study - loss-of-coolant accidents, core melt accidents, fires and external hazards, component aging, etc. -, the remaining uncertainties and, in some cases, new measures that should be developed to consolidate the safety of today's reactors and also those of tomorrow. A chapter of this report is also devoted to research into human and organizational factors, and the human and social sciences more generally. All of the work is reviewed in the light of the safety issues raised by feedback from major accidents such as Chernobyl and Fukushima Daiichi, as well as the issues raised by assessments conducted, for example, as part of the ten-year reviews of safety at French nuclear reactors. Finally, through the subjects it discusses, this report illustrates the many partnerships and exchanges forged by IRSN with public, industrial and academic bodies both within Europe and internationally. This publication reflects IRSN's desire to keep an enduring record of its results and to share its knowledge.</subfield></datafield><datafield tag="505" ind1="0" ind2="0"><subfield code="t">Frontmatter -- </subfield><subfield code="t">Preface -- </subfield><subfield code="t">The authors -- </subfield><subfield code="t">List of abbreviations -- </subfield><subfield code="t">Foreword -- </subfield><subfield code="t">Contents -- </subfield><subfield code="t">Chapter 1. Introduction -- </subfield><subfield code="t">Chapter 2. Some of the Research Facilities Favored by IRSN in the Field of Nuclear Power Reactor Safety -- </subfield><subfield code="t">Chapter 3. Research on Loss-of-coolant Accidents -- </subfield><subfield code="t">Chapter 4. Research on Reactivity-initiated Accidents -- </subfield><subfield code="t">Chapter 5. Research on Recirculation Cooling under Accident Conditions -- </subfield><subfield code="t">Chapter 6. Research on Spent Fuel Pool Uncovery Accidents -- </subfield><subfield code="t">Chapter 7. Research on Fires -- </subfield><subfield code="t">Chapter 8. Research on Hazards associated to Natural Events -- </subfield><subfield code="t">Chapter 9. Research on Core Melt Accidents -- </subfield><subfield code="t">Chapter 10. Research on the Behavior of Components Important to the Safety of NPPs and More Particularly the Aging of Such Components -- </subfield><subfield code="t">Chapter 11. Research in the Field of Human and Organizational Factors and, More Broadly, in Human and Social Sciences -- </subfield><subfield code="t">Chapter 12. Other Research and Tracks of New Research</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Water cooled reactors.</subfield></datafield><datafield tag="650" ind1=" " ind2="0"><subfield code="a">Nuclear reactors</subfield><subfield code="x">Security measures.</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Schwarz, Michel,</subfield><subfield code="e">author.</subfield></datafield><datafield tag="776" ind1=" " ind2=" "><subfield code="z">2-7598-2165-X</subfield></datafield><datafield tag="830" ind1=" " ind2="0"><subfield code="a">Science &amp; technology series.</subfield></datafield><datafield tag="906" ind1=" " ind2=" "><subfield code="a">BOOK</subfield></datafield><datafield tag="ADM" ind1=" " ind2=" "><subfield code="b">2024-06-10 01:19:20 Europe/Vienna</subfield><subfield code="f">system</subfield><subfield code="c">marc21</subfield><subfield code="a">2018-05-12 18:41:47 Europe/Vienna</subfield><subfield code="g">false</subfield></datafield><datafield tag="AVE" ind1=" " ind2=" "><subfield code="i">DOAB Directory of Open Access Books</subfield><subfield code="P">DOAB Directory of Open Access Books</subfield><subfield code="x">https://eu02.alma.exlibrisgroup.com/view/uresolver/43ACC_OEAW/openurl?u.ignore_date_coverage=true&amp;portfolio_pid=5338853570004498&amp;Force_direct=true</subfield><subfield code="Z">5338853570004498</subfield><subfield code="b">Available</subfield><subfield code="8">5338853570004498</subfield></datafield></record></collection>