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Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment Deterministic Evaluation for the Integrity of Reactor Pressure Vessel

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Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment Deterministic Evaluation for the Integrity of Reactor Pressure Vessel IAEA-TECDOC-1627 Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment Deterministic Evaluation for the Integrity of Reactor Pressure Vessel Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment Deterministic Evaluation for the Integrity of Reactor Pressure Vessel The following States are Members of the International Atomic Energy Agency: AFGHANISTAN GHANA NORWAY ALBANIA GREECE OMAN ALGERIA GUATEMALA PAKISTAN ANGOLA HAITI PALAU ARGENTINA HOLY SEE PANAMA ARMENIA HONDURAS PARAGUAY AUSTRALIA HUNGARY PERU AUSTRIA ICELAND PHILIPPINES AZERBAIJAN INDIA POLAND BAHRAIN INDONESIA PORTUGAL BANGLADESH IRAN, ISLAMIC REPUBLIC OF QATAR BELARUS IRAQ REPUBLIC OF MOLDOVA BELGIUM IRELAND ROMANIA BELIZE ISRAEL RUSSIAN FEDERATION BENIN ITALY SAUDI ARABIA BOLIVIA JAMAICA BOSNIA AND HERZEGOVINA JAPAN SENEGAL BOTSWANA JORDAN SERBIA BRAZIL KAZAKHSTAN SEYCHELLES BULGARIA KENYA SIERRA LEONE BURKINA FASO KOREA, REPUBLIC OF SINGAPORE BURUNDI KUWAIT SLOVAKIA CAMBODIA KYRGYZSTAN SLOVENIA CAMEROON LATVIA SOUTH AFRICA CANADA LEBANON SPAIN CENTRAL AFRICAN LESOTHO SRI LANKA REPUBLIC LIBERIA SUDAN CHAD LIBYAN ARAB JAMAHIRIYA SWEDEN CHILE LIECHTENSTEIN SWITZERLAND CHINA LITHUANIA SYRIAN ARAB REPUBLIC COLOMBIA LUXEMBOURG TAJIKISTAN CONGO MADAGASCAR THAILAND COSTA RICA MALAWI THE FORMER YUGOSLAV CÔTE D’IVOIRE MALAYSIA REPUBLIC OF MACEDONIA CROATIA MALI TUNISIA CUBA MALTA TURKEY CYPRUS MARSHALL ISLANDS UGANDA CZECH REPUBLIC MAURITANIA UKRAINE DEMOCRATIC REPUBLIC MAURITIUS UNITED ARAB EMIRATES OF THE CONGO MEXICO UNITED KINGDOM OF DENMARK MONACO GREAT BRITAIN AND DOMINICAN REPUBLIC MONGOLIA NORTHERN IRELAND ECUADOR MONTENEGRO EGYPT MOROCCO UNITED REPUBLIC EL SALVADOR MOZAMBIQUE OF TANZANIA ERITREA MYANMAR UNITED STATES OF AMERICA ESTONIA NAMIBIA URUGUAY ETHIOPIA NEPAL UZBEKISTAN FINLAND NETHERLANDS VENEZUELA FRANCE NEW ZEALAND VIETNAM GABON NICARAGUA YEMEN GEORGIA NIGER ZAMBIA GERMANY NIGERIA ZIMBABWE The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world’’. IAEA-TECDOC-1627 Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment Deterministic Evaluation for the Integrity of Reactor Pressure Vessel INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2010 COPYRIGHT NOTICE All IAEA scientific and technical publications are protected by the terms of the Universal Copyright Convention as adopted in 1952 (Berne) and as revised in 1972 (Paris). The copyright has since been extended by the World Intellectual Property Organization (Geneva) to include electronic and virtual intellectual property. Permission to use whole or parts of texts contained in IAEA publications in printed or electronic form must be obtained and is usually subject to royalty agreements. Proposals for non-commercial reproductions and translations are welcomed and considered on a case-by-case basis. Enquiries should be addressed to the IAEA Publishing Section at: Sales and Promotion, Publishing Section International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna, Austria fax: +43 1 2600 29302 tel.: +43 1 2600 22417 email: [email protected] http://www.iaea.org/books For further information on this publication, please contact: Nuclear Power Engineering Section International Atomic Energy Agency Vienna International Centre P.O. Box 100 1400 Vienna, Austria PRESSURIZED THERMAL SHOCK IN NUCLEAR POWER PLANTS: GOOD PRACTICES FOR ASSESSMENT IAEA, VIENNA, 2010 IAEA-TECDOC-1627 ISBN 978-92-0-111109-8 ISSN 1011-4289 © IAEA, 2010 Printed by the IAEA in Austria February 2010 FOREWORD Starting in the early 1970s, a series of coordinated research projects (CRPs) was sponsored by the IAEA focusing on the effects of neutron radiation on reactor pressure vessel (RPV) steels and RPV integrity. In conjunction with these CRPs, many consultants meetings, specialists meetings, and international conferences, dating back to the mid-1960s, were held. Individual studies on the basic phenomena of radiation hardening and embrittlement were also performed to better understand increases in tensile strength and shifts to higher temperatures for the integrity of the RPV. The overall objective of this CRP was to perform benchmark deterministic calculations of a typical pressurized thermal shock (PTS) regime, with the aim of comparing the effects of individual parameters on the final RPV integrity assessment, and then to recommend the best practices for their implementation in PTS procedures. At present, several different procedures and approaches are used for RPV integrity assessment for both WWER 440-230 reactors and pressurized water reactors (PWRs). These differences in procedures and approaches are based, in principle, on the different codes and rules used for design and manufacturing, and the different materials used for the various types of reactor, and the different levels of implementation of recent developments in fracture mechanics. Benchmark calculations were performed to improve user qualification and to reduce the user effect on the results of the analysis. This addressed generic PWR and WWER types of RPV, as well as sensitivity analyses. The complementary sensitivity analyses showed that the following factors significantly influenced the assessment: flaw size, shape, location and orientation, thermal hydraulic assumptions and material toughness. Applying national codes and procedures to the benchmark cases produced significantly different results in terms of allowable material toughness. This was mainly related to the safety factors used and the approaches to postulated defects, postulated transients and representation of material toughness. The IAEA wishes to thank the participants for their contributions, especially the CRP chairman, M. Brumovský of Nuclear Research Institute Řež plc, Czech Republic. The IAEA officers responsible for this publication were K.S. Kang and L. Kupca of the Division of Nuclear Power. EDITORIAL NOTE The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. CONTENTS 1. INTRODUCTION......................................................................................................................... 1 1.1. Background.......................................................................................................................... 1 1.2. RPV integrity studies........................................................................................................... 2 1.3. Coordinated research project - 9.......................................................................................... 4 1.4. Structure............................................................................................................................... 6 1.5. Results of benchmark calculations including sensitivity study ........................................... 7 1.6. References ........................................................................................................................... 8 2. SELECTION OF OVERCOOLING SEQUENCES ..................................................................... 9 2.1. General considerations......................................................................................................... 9 2.2. Precursors ............................................................................................................................ 9 2.3. Categorization of sequences of initiating events and corresponding criteria .................... 11 2.4. Initiating events groups...................................................................................................... 11 2.5. References ......................................................................................................................... 13 3. THERMAL HYDRAULIC ANALYSES ................................................................................... 14 3.1. Sequence analysis plan ...................................................................................................... 14 3.2. Calculation method requirements ...................................................................................... 14 3.3. Boundary conditions.......................................................................................................... 15 3.3.1. Plant operating conditions .................................................................................... 15 3.3.2. Symmetric cooling................................................................................................ 16 3.3.3. Plume cooling....................................................................................................... 16 3.3.4. Failures ................................................................................................................. 17 3.4. Operator actions................................................................................................................
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