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Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants PDF

174 Pages·2011·1.75 MB·English
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IA E A -T E C D O IAEA-TECDOC-1661 C -1 6 6 1 n M IT Ig A T IO n O f H y D r O g E n H A z A r D s In sE Mitigation of Hydrogen Hazards in v E r E A Severe Accidents in C C ID E n T Nuclear Power Plants s In n u C l E A r P O w E r P l A n T s INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–116510–7 ISSN 1011–4289 IAEA SAFETY RELATED PUBLICATIONS IAEA SAFETY STANDARDS Under the terms of Article III of its Statute, the IAEA is authorized to establish or adopt standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards. The publications by means of which the IAEA establishes standards are issued in the IAEA Safety Standards Series. This series covers nuclear safety, radiation safety, transport safety and waste safety. The publication categories in the series are Safety Fundamentals, Safety Requirements and Safety Guides. Information on the IAEA’s safety standards programme is available at the IAEA Internet site http://www-ns.iaea.org/standards/ The site provides the texts in English of published and draft safety standards. The texts of safety standards issued in Arabic, Chinese, French, Russian and Spanish, the IAEA Safety Glossary and a status report for safety standards under development are also available. For further information, please contact the IAEA at PO Box 100, 1400 Vienna, Austria. All users of IAEA safety standards are invited to inform the IAEA of experience in their use (e.g. as a basis for national regulations, for safety reviews and for training courses) for the purpose of ensuring that they continue to meet users’ needs. Information may be provided via the IAEA Internet site or by post, as above, or by email to [email protected]. OTHER SAFETY RELATED PUBLICATIONS The IAEA provides for the application of the standards and, under the terms of Articles III and VIII.C of its Statute, makes available and fosters the exchange of information relating to peaceful nuclear activities and serves as an intermediary among its Member States for this purpose. Reports on safety and protection in nuclear activities are issued as Safety Reports, which provide practical examples and detailed methods that can be used in support of the safety standards. Other safety related IAEA publications are issued as Radiological Assessment Reports, the International Nuclear Safety Group’s INSAG Reports, Technical Reports and TECDOCs. The IAEA also issues reports on radiological accidents, training manuals and practical manuals, and other special safety related publications. Security related publications are issued in the IAEA Nuclear Security Series. Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants 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 SENEGAL BOSNIA AND HERZEGOVINA JAPAN SERBIA BOTSWANA JORDAN 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 UNITED REPUBLIC EGYPT MOROCCO OF TANZANIA EL SALVADOR MOZAMBIQUE UNITED STATES OF AMERICA ERITREA MYANMAR URUGUAY ESTONIA NAMIBIA 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-1661 MITIGATION OF HYDROGEN HAZARDS IN SEVERE ACCIDENTS IN NUCLEAR POWER PLANTS INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, 2011 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: Safety Assessment Section International Atomic Energy Agency Vienna International Centre PO Box 100 1400 Vienna, Austria email: [email protected] MITIGATION OF HYDROGEN HAZARDS IN SEVERE ACCIDENTS IN NUCLEAR POWER PLANTS IAEA, VIENNA, 2011 IAEA-TECDOC-1661 ISBN 978-92-0-116510-7 ISSN 1011-4289 © IAEA, 2011 Printed by the IAEA in Austria July 2011 FOREWORD Consideration of severe accidents in nuclear power plants is an essential component of the defence in depth approach in nuclear safety. Severe accidents have very low probabilities of occurring, but may have significant consequences resulting from the degradation of nuclear fuel. The generation of hydrogen and the risk of hydrogen combustion, as well as other phenomena leading to overpressurization of the reactor containment in case of severe accidents, represent complex safety issues in relation to accident management. The combustion of hydrogen, produced primarily as a result of heated zirconium metal reacting with steam, can create short term overpressure or detonation forces that may exceed the strength of the containment structure. An understanding of these phenomena is crucial for planning and implementing effective accident management measures. Analysis of all the issues relating to hydrogen risk is an important step for any measure that is aimed at the prevention or mitigation of hydrogen combustion in reactor containments. The main objective of this publication is to contribute to the implementation of IAEA Safety Standards, in particular, two IAEA Safety Requirements: Safety of Nuclear Power Plants: Design and Safety of Nuclear Power Plants: Operation. These Requirements publications discuss computational analysis of severe accidents and accident management programmes in nuclear power plants. Specifically with regard to the risk posed by hydrogen in nuclear power reactors, computational analysis of severe accidents considers hydrogen sources, hydrogen distribution, hydrogen combustion and control and mitigation measures for hydrogen, while accident management programmes are aimed at mitigating hydrogen hazards in reactor containments. The IAEA staff member responsible for this publication was C.O. Park of the Division of Nuclear Installation Safety. 1 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. OBJECTIVE AND SCOPE ...................................................................................................... 5 1.3. STRUCTURE ....................................................................................................................... 5 2. POTENTIAL HYDROGEN SOURCES DURING THE EVOLUTION OF A SEVERE ACCIDENT ............................................................................................................ 6 2.1. INTRODUCTION .................................................................................................................. 6 2.2. IN-VESSEL HYDROGEN SOURCE ......................................................................................... 7 2.2.1. Short description of core degradation during a severe accident ................................ 7 2.2.2. In-vessel hydrogen source from Zr oxidation............................................................ 9 2.2 3. In-vessel hydrogen production coming from steel oxidation .................................. 14 2.2.4. In-vessel hydrogen production coming from B C absorber material oxidation ...... 14 4 2.2.5. Consequences to be drawn regarding calculations .................................................. 16 2.3. EX-VESSEL HYDROGEN PRODUCTION .............................................................................. 16 2.3.1. Short term H release during vessel lower head failure ........................................... 16 2 2.3.2. H production during molten core-concrete interaction .......................................... 17 2 2.3.3. Other possible ex-vessel H production ................................................................... 19 2 3. HYDROGEN DISTRIBUTION .......................................................................................... 19 3.1. DESCRIPTION OF CONTAINMENT ...................................................................................... 20 3.1.1. Full pressure containment ........................................................................................ 20 3.1.2. Containments with pressure suppression system ..................................................... 21 3.2. LOCATION OF HYDROGEN SOURCES IN THE CONTAINMENT .............................................. 23 3.3. EFFECT OF RELEASE MODE AND SPRAYING ON HYDROGEN DISTRIBUTION ....................... 23 3.4. CONTAINMENT LAYOUT EFFECTS .................................................................................... 24 3.5. ANALYTICAL TOOLS ........................................................................................................ 25 3.5.1. Integrated codes or system codes ............................................................................ 25 3.5.2. Lumped parameter codes ......................................................................................... 25 3.5.3. Computational fluid dynamics codes ...................................................................... 26 3.5.4. Hybrid codes ............................................................................................................ 28 3.5.5. Comparison of general advantages and disadvantages of the different code types. 29 3.6. EXPERIMENTAL FACILITIES TO MEASURE HYDROGEN DISTRIBUTIONS ........................... 29 3.6.1. Gas distribution experiments for large dry containments ........................................ 29 3.6.2. Experiments for ice condenser containments .......................................................... 31 3.6.3. Recent and future experiments ................................................................................ 31 4. HYDROGEN COMBUSTION ............................................................................................ 33 4.1. INTRODUCTION ................................................................................................................ 33 4.2. FLAMMABILITY AND IGNITION CONDITIONS .................................................................... 34 4.2.1. Flammability ............................................................................................................ 34 4.2.2. Auto ignition and ignition ........................................................................................ 35 4.3. MODES OF COMBUSTION ................................................................................................. 36 4.3.1. Deflagration ............................................................................................................. 36 4.3.2. Detonation ............................................................................................................... 36 4.3.3. Flame acceleration and deflagration to-detonation transition ................................. 38 4.3.4. Quenching ................................................................................................................ 41 4.3.5. Mechanisms involved in Deflagration to Detonation Transition ............................ 41 4.3.6. Necessary criteria for flame acceleration and DDT ................................................ 41 4.3.7. Diffusion flames ...................................................................................................... 46 4.3.8. Effect of carbon monoxide ...................................................................................... 47 4.3.9. Pressure loads associated with different combustion phenomena ........................... 48 4.4. ANALYTICAL TOOLS ........................................................................................................ 49 4.4.1. Combustion in containment systems codes (lumped parameter) ............................ 49 4.4.2. Combustion in CFD codes ....................................................................................... 50 4.5. EXPERIMENTAL FACILITIES ............................................................................................. 54 4.5.1. Small scale facilities ................................................................................................ 54 4.5.2. Medium test facilities .............................................................................................. 56 4.5.3. Experiments in large scale and complex geometries ............................................... 56 5. RISK FROM HYDROGEN COMBUSTION...................................................................... 58 5.1. COMBUSTION LOADS AND STRUCTURAL RESPONSE ......................................................... 58 5.2. THREATS FROM COMBUSTION TO THE CONTAINMENT ...................................................... 60 5.2.1. Direct damage. ......................................................................................................... 60 5.2.2. Indirect damage ....................................................................................................... 61 5.2.3. Failure of secondary containment ............................................................................ 62 5.2.4. Failure of containment vent. .................................................................................... 62 5.2.5. Effect of temperature. .............................................................................................. 63 5.3. SCENARIO EFFECTS ......................................................................................................... 63 5.4. OTHER FACTORS RELEVANT FOR THE RISK FROM COMBUSTION GASES ............................ 64 5.4.1. Other substances than hydrogen. ............................................................................. 64 5.4.2. Pressure build-up by non-condensables. ................................................................. 64 5.4.3. Stratification of gases .............................................................................................. 65 5.4.4. Effects from accident management ......................................................................... 65 5.5. SENSITIVITY OF VARIOUS CONTAINMENTS TO HYDROGEN COMBUSTION LOADS .............. 66 5.5.1. Large dry containment ............................................................................................. 67 5.5.2. Ice condenser containment ...................................................................................... 67 5.5.3. Suppression pool containment (BWR) .................................................................... 67 5.5.4. WWER confinement................................................................................................ 67 5.5.5. Future designs .......................................................................................................... 68 5.6. TREATMENT OF HYDROGEN IN THE PSA ......................................................................... 70 6. HYDROGEN MEASUREMENT ........................................................................................ 71 6.1. OBJECTIVES OF A H2 MEASUREMENT SYSTEM ................................................................. 71 6.2. H2 MEASUREMENT SYSTEMS ............................................................................................ 71 6.2.1. Hydrogen concentration measurement system inside the containment ................... 72 6.2.2. Systems based on sampling ..................................................................................... 72 6.3. H2 MEASUREMENT SYSTEMS QUALIFICATION .................................................................. 73 6.4. H2 MEASUREMENT PROBE POSITION ................................................................................ 73 6.5. H2 MEASUREMENT EVALUATION WITHOUT ANY H2 MEASUREMENT ................................ 73 7. HYDROGEN CONTROL AND RISK MITIGATION ....................................................... 73 7.1. INERTIZATION OF THE CONTAINMENT ATMOSPHERE ........................................................ 74 7.1.1. Pre-inertization ........................................................................................................ 74 7.1.2. Post-inertization ....................................................................................................... 74

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Safety Standards, in particular, two IAEA Safety Requirements: Safety of Nuclear Power. Plants: in nuclear power reactors, computational analysis of severe accidents considers hydrogen sources challenges to the containment integrity during a severe accident in a light water reactor. (LWR).
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