Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
Identifieur interne : 003596 ( Main/Repository ); précédent : 003595; suivant : 003597Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
Auteurs : RBID : Pascal:10-0179404Descripteurs français
- Pascal (Inist)
- Argent, Indium, Cadmium, Barre contrôle, Réacteur eau pressurisée, Réacteur nucléaire, Accident, Carbure de silicium, Barre combustible, Dégradation, Gaine (combustible), Circuit refroidissement, Modélisation, Projet, Code calcul, Rupture, Thermodynamique, Géométrie, Simulateur, Mesure pression, Aérosol.
- Wicri :
- concept : Argent, Cadmium, Réacteur nucléaire, Thermodynamique, Aérosol.
English descriptors
- KwdEn :
Abstract
In the case of a hypothetical severe accident in a Pressurized Water Reactor (PWR), Silver-Indium-Cadmium (SIC) control rod failure occurs early during the sequence. Release of absorber melt could induce early fuel rod degradation by interaction of molten SIC alloy with fuel rod cladding, and the absorber materials could interact with the fission products, affecting significantly their speciation and transport in the primary circuit as well as their behaviour in the containment. This paper summarises the experimental and modelling progress made on this topic within SARNET over the whole project. Following a review of the status of knowledge, including the modelling in the main severe accident codes (ATHLET-CD, MAAP4, SCDAP, MELCOR, ASTEC), detailed calculations of the specific EMAIC and integral PHEBUS FPT2 experiments were performed. Accurate calculation of vapour pressure of the molten absorber elements is needed, requiring reliable values of the activity coefficients. The importance of accurate reproduction of the control rod degradation was shown, with the behaviour of absorber elements at rupture being critical as well as the thermodynamic data and speciation of the system Ag-In-Cd-Zr-H-O. The QUENCH-13 bundle experiment (FZK), conducted with a realistic integral geometry composed of 20 electrical heated rod simulators and one central SIC absorber rod, has helped to characterize the behaviour of absorber elements at the time of rod rupture, with measurements of the SIC release, using impactors (AEKI) and electrical low-pressure impactor and Berner low-pressure impactors (PSI). Coordinated pre and post-test calculations using SCDAP/RELAP5 based codes (PSI), MAAP4 (EDF), ATHLET-CD (GRS), ASTEC (IRSN) helped in defining the test and in its interpretation. Before this experiment, five tests were performed on small-scale SIC control rod samples using different designs and conditions. They helped in defining the conditions for the QUENCH-13 experiment. Five additional tests on similar small-scale samples are foreseen to help interpretation of the QUENCH-13 results. In QUENCH-13 the on-line aerosol measurements with electrical low-pressure impactors indicated control rod failure in the range 1550-1600 K; the test was terminated later at 1813 K by water reflood. Analysis of aerosols measured at sample points in the off-gas line showed significant Cd and In transport after rod failure with a smaller amount of transported Ag. Relocated SIC melt in the form of rivulets was detected in the lower part of the bundle. Investigation of SIC material properties (solidus, liquidus) by further analysis of data from QUENCH-13 is also presented. In parallel, an exhaustive review of activity coefficients of the elements in the SIC melt, including the effect of Zr was began (IRSN with the CNRS Marseille).
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<record><TEI><teiHeader><fileDesc><titleStmt><title xml:lang="en" level="a">Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences</title><author><name sortKey="Dubourg, R" uniqKey="Dubourg R">R. Dubourg</name><affiliation wicri:level="3"><inist:fA14 i1="02"><s1>Institut de Radioprotection et de Sûreté Nucléaire (IRSN), DPAM - Bat 250, BP 3</s1><s2>13115 St Paul-Lez-Durance</s2><s3>FRA</s3><sZ>1 aut.</sZ><sZ>4 aut.</sZ><sZ>6 aut.</sZ><sZ>10 aut.</sZ></inist:fA14><country>France</country><placeName><region type="region" nuts="2">Provence-Alpes-Côte d'Azur</region><settlement type="city">St Paul-Lez-Durance</settlement></placeName></affiliation></author><author><name sortKey="Austregesilo, H" uniqKey="Austregesilo H">H. Austregesilo</name><affiliation wicri:level="1"><inist:fA14 i1="01"><s1>GRS mbH, Forschungsgeldnde</s1><s2>85748 Garching</s2><s3>DEU</s3><sZ>2 aut.</sZ><sZ>3 aut.</sZ><sZ>14 aut.</sZ><sZ>15 aut.</sZ></inist:fA14><country>Allemagne</country><wicri:noRegion>85748 Garching</wicri:noRegion><wicri:noRegion>Forschungsgeldnde</wicri:noRegion><wicri:noRegion>85748 Garching</wicri:noRegion></affiliation></author><author><name sortKey="Bals, C" uniqKey="Bals C">C. Bals</name><affiliation wicri:level="1"><inist:fA14 i1="01"><s1>GRS mbH, Forschungsgeldnde</s1><s2>85748 Garching</s2><s3>DEU</s3><sZ>2 aut.</sZ><sZ>3 aut.</sZ><sZ>14 aut.</sZ><sZ>15 aut.</sZ></inist:fA14><country>Allemagne</country><wicri:noRegion>85748 Garching</wicri:noRegion><wicri:noRegion>Forschungsgeldnde</wicri:noRegion><wicri:noRegion>85748 Garching</wicri:noRegion></affiliation></author><author><name sortKey="Barrachin, M" uniqKey="Barrachin M">M. Barrachin</name><affiliation wicri:level="3"><inist:fA14 i1="02"><s1>Institut de Radioprotection et de Sûreté Nucléaire (IRSN), DPAM - Bat 250, BP 3</s1><s2>13115 St Paul-Lez-Durance</s2><s3>FRA</s3><sZ>1 aut.</sZ><sZ>4 aut.</sZ><sZ>6 aut.</sZ><sZ>10 aut.</sZ></inist:fA14><country>France</country><placeName><region type="region" nuts="2">Provence-Alpes-Côte d'Azur</region><settlement type="city">St Paul-Lez-Durance</settlement></placeName></affiliation></author><author><name sortKey="Birchley, J" uniqKey="Birchley J">J. Birchley</name><affiliation wicri:level="1"><inist:fA14 i1="03"><s1>Paul Scherrer Institut (PSI), NES/LTH. OVGA/312</s1><s2>5232 Villigen PSI</s2><s3>CHE</s3><sZ>5 aut.</sZ><sZ>6 aut.</sZ><sZ>8 aut.</sZ></inist:fA14><country>Suisse</country><wicri:noRegion>5232 Villigen PSI</wicri:noRegion></affiliation></author><author><name sortKey="Haste, T" uniqKey="Haste T">T. Haste</name><affiliation wicri:level="3"><inist:fA14 i1="02"><s1>Institut de Radioprotection et de Sûreté Nucléaire (IRSN), DPAM - Bat 250, BP 3</s1><s2>13115 St Paul-Lez-Durance</s2><s3>FRA</s3><sZ>1 aut.</sZ><sZ>4 aut.</sZ><sZ>6 aut.</sZ><sZ>10 aut.</sZ></inist:fA14><country>France</country><placeName><region type="region" nuts="2">Provence-Alpes-Côte d'Azur</region><settlement type="city">St Paul-Lez-Durance</settlement></placeName></affiliation><affiliation wicri:level="1"><inist:fA14 i1="03"><s1>Paul Scherrer Institut (PSI), NES/LTH. OVGA/312</s1><s2>5232 Villigen PSI</s2><s3>CHE</s3><sZ>5 aut.</sZ><sZ>6 aut.</sZ><sZ>8 aut.</sZ></inist:fA14><country>Suisse</country><wicri:noRegion>5232 Villigen PSI</wicri:noRegion></affiliation></author><author><name sortKey="Lamy, J S" uniqKey="Lamy J">J. S. Lamy</name><affiliation wicri:level="3"><inist:fA14 i1="04"><s1>EDF, R&D, 1 avenue du Général de Gaulle</s1><s2>92141 Clamart</s2><s3>FRA</s3><sZ>7 aut.</sZ><sZ>9 aut.</sZ></inist:fA14><country>France</country><placeName><region type="region" nuts="2">Île-de-France</region><settlement type="city">Clamart</settlement></placeName></affiliation></author><author><name sortKey="Lind, T" uniqKey="Lind T">T. Lind</name><affiliation wicri:level="1"><inist:fA14 i1="03"><s1>Paul Scherrer Institut (PSI), NES/LTH. OVGA/312</s1><s2>5232 Villigen PSI</s2><s3>CHE</s3><sZ>5 aut.</sZ><sZ>6 aut.</sZ><sZ>8 aut.</sZ></inist:fA14><country>Suisse</country><wicri:noRegion>5232 Villigen PSI</wicri:noRegion></affiliation></author><author><name sortKey="Maliverney, B" uniqKey="Maliverney B">B. Maliverney</name><affiliation wicri:level="3"><inist:fA14 i1="04"><s1>EDF, R&D, 1 avenue du Général de Gaulle</s1><s2>92141 Clamart</s2><s3>FRA</s3><sZ>7 aut.</sZ><sZ>9 aut.</sZ></inist:fA14><country>France</country><placeName><region type="region" nuts="2">Île-de-France</region><settlement type="city">Clamart</settlement></placeName></affiliation></author><author><name sortKey="Marchetto, C" uniqKey="Marchetto C">C. Marchetto</name><affiliation wicri:level="3"><inist:fA14 i1="02"><s1>Institut de Radioprotection et de Sûreté Nucléaire (IRSN), DPAM - Bat 250, BP 3</s1><s2>13115 St Paul-Lez-Durance</s2><s3>FRA</s3><sZ>1 aut.</sZ><sZ>4 aut.</sZ><sZ>6 aut.</sZ><sZ>10 aut.</sZ></inist:fA14><country>France</country><placeName><region type="region" nuts="2">Provence-Alpes-Côte d'Azur</region><settlement type="city">St Paul-Lez-Durance</settlement></placeName></affiliation></author><author><name sortKey="Pinter, A" uniqKey="Pinter A">A. Pinter</name><affiliation wicri:level="1"><inist:fA14 i1="05"><s1>AEKI, Fuel Materials Department, HAS KFKI AEKI</s1><s2>1121 Budapest</s2><s3>HUN</s3><sZ>11 aut.</sZ></inist:fA14><country>Hongrie</country><placeName><settlement type="city">Budapest</settlement><region nuts="2">Hongrie centrale</region></placeName></affiliation></author><author><name sortKey="Steinbruck, M" uniqKey="Steinbruck M">M. Steinbruck</name><affiliation wicri:level="3"><inist:fA14 i1="06"><s1>Forschungzentrum Karlsruhe (FZK) GmbH, Postfach 3640</s1><s2>76021 Karlsruhe</s2><s3>DEU</s3><sZ>12 aut.</sZ><sZ>13 aut.</sZ></inist:fA14><country>Allemagne</country><placeName><region type="land" nuts="1">Bade-Wurtemberg</region><region type="district" nuts="2">District de Karlsruhe</region><settlement type="city">Karlsruhe</settlement></placeName></affiliation></author><author><name sortKey="Stuckert, J" uniqKey="Stuckert J">J. Stuckert</name><affiliation wicri:level="3"><inist:fA14 i1="06"><s1>Forschungzentrum Karlsruhe (FZK) GmbH, Postfach 3640</s1><s2>76021 Karlsruhe</s2><s3>DEU</s3><sZ>12 aut.</sZ><sZ>13 aut.</sZ></inist:fA14><country>Allemagne</country><placeName><region type="land" nuts="1">Bade-Wurtemberg</region><region type="district" nuts="2">District de Karlsruhe</region><settlement type="city">Karlsruhe</settlement></placeName></affiliation></author><author><name sortKey="Trambauer, K" uniqKey="Trambauer K">K. Trambauer</name><affiliation wicri:level="1"><inist:fA14 i1="01"><s1>GRS mbH, Forschungsgeldnde</s1><s2>85748 Garching</s2><s3>DEU</s3><sZ>2 aut.</sZ><sZ>3 aut.</sZ><sZ>14 aut.</sZ><sZ>15 aut.</sZ></inist:fA14><country>Allemagne</country><wicri:noRegion>85748 Garching</wicri:noRegion><wicri:noRegion>Forschungsgeldnde</wicri:noRegion><wicri:noRegion>85748 Garching</wicri:noRegion></affiliation></author><author><name sortKey="Vimi, A" uniqKey="Vimi A">A. Vimi</name><affiliation wicri:level="1"><inist:fA14 i1="01"><s1>GRS mbH, Forschungsgeldnde</s1><s2>85748 Garching</s2><s3>DEU</s3><sZ>2 aut.</sZ><sZ>3 aut.</sZ><sZ>14 aut.</sZ><sZ>15 aut.</sZ></inist:fA14><country>Allemagne</country><wicri:noRegion>85748 Garching</wicri:noRegion><wicri:noRegion>Forschungsgeldnde</wicri:noRegion><wicri:noRegion>85748 Garching</wicri:noRegion></affiliation></author></titleStmt><publicationStmt><idno type="inist">10-0179404</idno><date when="2010">2010</date><idno type="stanalyst">PASCAL 10-0179404 INIST</idno><idno type="RBID">Pascal:10-0179404</idno><idno type="wicri:Area/Main/Corpus">004708</idno><idno type="wicri:Area/Main/Repository">003596</idno></publicationStmt><seriesStmt><idno type="ISSN">0149-1970</idno><title level="j" type="abbreviated">Prog. nucl. energy : (New ser.)</title><title level="j" type="main">Progress in nuclear energy : (New series)</title></seriesStmt></fileDesc><profileDesc><textClass><keywords scheme="KwdEn" xml:lang="en"><term>Accident</term><term>Aerosols</term><term>Cadmium</term><term>Clad</term><term>Computation code</term><term>Control rod</term><term>Cooling circuit</term><term>Degradation</term><term>Fuel rod</term><term>Geometry</term><term>Indium</term><term>Modeling</term><term>Nuclear reactor</term><term>Pressure measurement</term><term>Pressurized water reactor</term><term>Project</term><term>Rupture</term><term>Silicon carbide</term><term>Silver</term><term>Simulator</term><term>Thermodynamics</term></keywords><keywords scheme="Pascal" xml:lang="fr"><term>Argent</term><term>Indium</term><term>Cadmium</term><term>Barre contrôle</term><term>Réacteur eau pressurisée</term><term>Réacteur nucléaire</term><term>Accident</term><term>Carbure de silicium</term><term>Barre combustible</term><term>Dégradation</term><term>Gaine (combustible)</term><term>Circuit refroidissement</term><term>Modélisation</term><term>Projet</term><term>Code calcul</term><term>Rupture</term><term>Thermodynamique</term><term>Géométrie</term><term>Simulateur</term><term>Mesure pression</term><term>Aérosol</term></keywords><keywords scheme="Wicri" type="concept" xml:lang="fr"><term>Argent</term><term>Cadmium</term><term>Réacteur nucléaire</term><term>Thermodynamique</term><term>Aérosol</term></keywords></textClass></profileDesc></teiHeader><front><div type="abstract" xml:lang="en">In the case of a hypothetical severe accident in a Pressurized Water Reactor (PWR), Silver-Indium-Cadmium (SIC) control rod failure occurs early during the sequence. Release of absorber melt could induce early fuel rod degradation by interaction of molten SIC alloy with fuel rod cladding, and the absorber materials could interact with the fission products, affecting significantly their speciation and transport in the primary circuit as well as their behaviour in the containment. This paper summarises the experimental and modelling progress made on this topic within SARNET over the whole project. Following a review of the status of knowledge, including the modelling in the main severe accident codes (ATHLET-CD, MAAP4, SCDAP, MELCOR, ASTEC), detailed calculations of the specific EMAIC and integral PHEBUS FPT2 experiments were performed. Accurate calculation of vapour pressure of the molten absorber elements is needed, requiring reliable values of the activity coefficients. The importance of accurate reproduction of the control rod degradation was shown, with the behaviour of absorber elements at rupture being critical as well as the thermodynamic data and speciation of the system Ag-In-Cd-Zr-H-O. The QUENCH-13 bundle experiment (FZK), conducted with a realistic integral geometry composed of 20 electrical heated rod simulators and one central SIC absorber rod, has helped to characterize the behaviour of absorber elements at the time of rod rupture, with measurements of the SIC release, using impactors (AEKI) and electrical low-pressure impactor and Berner low-pressure impactors (PSI). Coordinated pre and post-test calculations using SCDAP/RELAP5 based codes (PSI), MAAP4 (EDF), ATHLET-CD (GRS), ASTEC (IRSN) helped in defining the test and in its interpretation. Before this experiment, five tests were performed on small-scale SIC control rod samples using different designs and conditions. They helped in defining the conditions for the QUENCH-13 experiment. Five additional tests on similar small-scale samples are foreseen to help interpretation of the QUENCH-13 results. In QUENCH-13 the on-line aerosol measurements with electrical low-pressure impactors indicated control rod failure in the range 1550-1600 K; the test was terminated later at 1813 K by water reflood. Analysis of aerosols measured at sample points in the off-gas line showed significant Cd and In transport after rod failure with a smaller amount of transported Ag. Relocated SIC melt in the form of rivulets was detected in the lower part of the bundle. Investigation of SIC material properties (solidus, liquidus) by further analysis of data from QUENCH-13 is also presented. In parallel, an exhaustive review of activity coefficients of the elements in the SIC melt, including the effect of Zr was began (IRSN with the CNRS Marseille).</div></front></TEI><inist><standard h6="B"><pA><fA01 i1="01" i2="1"><s0>0149-1970</s0></fA01><fA03 i2="1"><s0>Prog. nucl. energy : (New ser.)</s0></fA03><fA05><s2>52</s2></fA05><fA06><s2>1</s2></fA06><fA08 i1="01" i2="1" l="ENG"><s1>Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences</s1></fA08><fA09 i1="01" i2="1" l="ENG"><s1>Major achievements after 4,5 years of SARNET Severe Accident Research Network of Excellence (6<sup>th</sup> European Reserach Framework Programme)</s1></fA09><fA11 i1="01" i2="1"><s1>DUBOURG (R.)</s1></fA11><fA11 i1="02" i2="1"><s1>AUSTREGESILO (H.)</s1></fA11><fA11 i1="03" i2="1"><s1>BALS (C.)</s1></fA11><fA11 i1="04" i2="1"><s1>BARRACHIN (M.)</s1></fA11><fA11 i1="05" i2="1"><s1>BIRCHLEY (J.)</s1></fA11><fA11 i1="06" i2="1"><s1>HASTE (T.)</s1></fA11><fA11 i1="07" i2="1"><s1>LAMY (J. S.)</s1></fA11><fA11 i1="08" i2="1"><s1>LIND (T.)</s1></fA11><fA11 i1="09" i2="1"><s1>MALIVERNEY (B.)</s1></fA11><fA11 i1="10" i2="1"><s1>MARCHETTO (C.)</s1></fA11><fA11 i1="11" i2="1"><s1>PINTER (A.)</s1></fA11><fA11 i1="12" i2="1"><s1>STEINBRUCK (M.)</s1></fA11><fA11 i1="13" i2="1"><s1>STUCKERT (J.)</s1></fA11><fA11 i1="14" i2="1"><s1>TRAMBAUER (K.)</s1></fA11><fA11 i1="15" i2="1"><s1>VIMI (A.)</s1></fA11><fA12 i1="01" i2="1"><s1>BAL RAJ SEHGAL</s1><s9>ed.</s9></fA12><fA12 i1="02" i2="1"><s1>VAN DORSSELAERE (Jean-Pierre)</s1><s9>ed.</s9></fA12><fA12 i1="03" i2="1"><s1>ALBIOL (Thierry)</s1><s9>ed.</s9></fA12><fA12 i1="04" i2="1"><s1>JACQUEMAIN (Didier)</s1><s9>ed.</s9></fA12><fA12 i1="05" i2="1"><s1>JOURNEAU (Christophe)</s1><s9>ed.</s9></fA12><fA14 i1="01"><s1>GRS mbH, Forschungsgeldnde</s1><s2>85748 Garching</s2><s3>DEU</s3><sZ>2 aut.</sZ><sZ>3 aut.</sZ><sZ>14 aut.</sZ><sZ>15 aut.</sZ></fA14><fA14 i1="02"><s1>Institut de Radioprotection et de Sûreté Nucléaire (IRSN), DPAM - Bat 250, BP 3</s1><s2>13115 St Paul-Lez-Durance</s2><s3>FRA</s3><sZ>1 aut.</sZ><sZ>4 aut.</sZ><sZ>6 aut.</sZ><sZ>10 aut.</sZ></fA14><fA14 i1="03"><s1>Paul Scherrer Institut (PSI), NES/LTH. OVGA/312</s1><s2>5232 Villigen PSI</s2><s3>CHE</s3><sZ>5 aut.</sZ><sZ>6 aut.</sZ><sZ>8 aut.</sZ></fA14><fA14 i1="04"><s1>EDF, R&D, 1 avenue du Général de Gaulle</s1><s2>92141 Clamart</s2><s3>FRA</s3><sZ>7 aut.</sZ><sZ>9 aut.</sZ></fA14><fA14 i1="05"><s1>AEKI, Fuel Materials Department, HAS KFKI AEKI</s1><s2>1121 Budapest</s2><s3>HUN</s3><sZ>11 aut.</sZ></fA14><fA14 i1="06"><s1>Forschungzentrum Karlsruhe (FZK) GmbH, Postfach 3640</s1><s2>76021 Karlsruhe</s2><s3>DEU</s3><sZ>12 aut.</sZ><sZ>13 aut.</sZ></fA14><fA15 i1="01"><s1>Kungl Tekniska Högskolan (KTH), AlbaNova University Center, Schwertnergrasse 1</s1><s2>50667 Köln</s2><s3>DEU</s3><sZ>1 aut.</sZ></fA15><fA15 i1="02"><s1>Institut de Radioprotection et de Sûreté Nucléaire (IRSN), DPAM - Bat 250, BP 3</s1><s2>13115 St-Paul-Lez-Durance</s2><s3>FRA</s3><sZ>2 aut.</sZ><sZ>3 aut.</sZ></fA15><fA15 i1="03"><s1>Commissariat à l'Energie Atomique (CEA), DEN/STRI/LMA, Cadarache</s1><s2>13115 St-Paul-Lez-Durance</s2><s3>FRA</s3><sZ>5 aut.</sZ></fA15><fA20><s1>97-108</s1></fA20><fA21><s1>2010</s1></fA21><fA23 i1="01"><s0>ENG</s0></fA23><fA43 i1="01"><s1>INIST</s1><s2>17686</s2><s5>354000186660820090</s5></fA43><fA44><s0>0000</s0><s1>© 2010 INIST-CNRS. All rights reserved.</s1></fA44><fA45><s0>1/4 p.</s0></fA45><fA47 i1="01" i2="1"><s0>10-0179404</s0></fA47><fA60><s1>P</s1><s2>C</s2></fA60><fA61><s0>A</s0></fA61><fA64 i1="01" i2="1"><s0>Progress in nuclear energy : (New series)</s0></fA64><fA66 i1="01"><s0>GBR</s0></fA66><fC01 i1="01" l="ENG"><s0>In the case of a hypothetical severe accident in a Pressurized Water Reactor (PWR), Silver-Indium-Cadmium (SIC) control rod failure occurs early during the sequence. Release of absorber melt could induce early fuel rod degradation by interaction of molten SIC alloy with fuel rod cladding, and the absorber materials could interact with the fission products, affecting significantly their speciation and transport in the primary circuit as well as their behaviour in the containment. This paper summarises the experimental and modelling progress made on this topic within SARNET over the whole project. Following a review of the status of knowledge, including the modelling in the main severe accident codes (ATHLET-CD, MAAP4, SCDAP, MELCOR, ASTEC), detailed calculations of the specific EMAIC and integral PHEBUS FPT2 experiments were performed. Accurate calculation of vapour pressure of the molten absorber elements is needed, requiring reliable values of the activity coefficients. The importance of accurate reproduction of the control rod degradation was shown, with the behaviour of absorber elements at rupture being critical as well as the thermodynamic data and speciation of the system Ag-In-Cd-Zr-H-O. The QUENCH-13 bundle experiment (FZK), conducted with a realistic integral geometry composed of 20 electrical heated rod simulators and one central SIC absorber rod, has helped to characterize the behaviour of absorber elements at the time of rod rupture, with measurements of the SIC release, using impactors (AEKI) and electrical low-pressure impactor and Berner low-pressure impactors (PSI). Coordinated pre and post-test calculations using SCDAP/RELAP5 based codes (PSI), MAAP4 (EDF), ATHLET-CD (GRS), ASTEC (IRSN) helped in defining the test and in its interpretation. Before this experiment, five tests were performed on small-scale SIC control rod samples using different designs and conditions. They helped in defining the conditions for the QUENCH-13 experiment. Five additional tests on similar small-scale samples are foreseen to help interpretation of the QUENCH-13 results. In QUENCH-13 the on-line aerosol measurements with electrical low-pressure impactors indicated control rod failure in the range 1550-1600 K; the test was terminated later at 1813 K by water reflood. Analysis of aerosols measured at sample points in the off-gas line showed significant Cd and In transport after rod failure with a smaller amount of transported Ag. Relocated SIC melt in the form of rivulets was detected in the lower part of the bundle. Investigation of SIC material properties (solidus, liquidus) by further analysis of data from QUENCH-13 is also presented. In parallel, an exhaustive review of activity coefficients of the elements in the SIC melt, including the effect of Zr was began (IRSN with the CNRS Marseille).</s0></fC01><fC02 i1="01" i2="X"><s0>001D06D04D</s0></fC02><fC02 i1="02" i2="X"><s0>230</s0></fC02><fC03 i1="01" i2="X" l="FRE"><s0>Argent</s0><s2>NC</s2><s2>FX</s2><s5>05</s5></fC03><fC03 i1="01" i2="X" l="ENG"><s0>Silver</s0><s2>NC</s2><s2>FX</s2><s5>05</s5></fC03><fC03 i1="01" i2="X" l="SPA"><s0>Plata</s0><s2>NC</s2><s2>FX</s2><s5>05</s5></fC03><fC03 i1="02" i2="X" l="FRE"><s0>Indium</s0><s2>NC</s2><s5>06</s5></fC03><fC03 i1="02" i2="X" l="ENG"><s0>Indium</s0><s2>NC</s2><s5>06</s5></fC03><fC03 i1="02" i2="X" l="SPA"><s0>Indio</s0><s2>NC</s2><s5>06</s5></fC03><fC03 i1="03" i2="X" l="FRE"><s0>Cadmium</s0><s2>NC</s2><s2>FX</s2><s5>07</s5></fC03><fC03 i1="03" i2="X" l="ENG"><s0>Cadmium</s0><s2>NC</s2><s2>FX</s2><s5>07</s5></fC03><fC03 i1="03" i2="X" l="SPA"><s0>Cadmio</s0><s2>NC</s2><s2>FX</s2><s5>07</s5></fC03><fC03 i1="04" i2="X" l="FRE"><s0>Barre contrôle</s0><s5>08</s5></fC03><fC03 i1="04" i2="X" l="ENG"><s0>Control rod</s0><s5>08</s5></fC03><fC03 i1="04" i2="X" l="SPA"><s0>Barra control</s0><s5>08</s5></fC03><fC03 i1="05" i2="X" l="FRE"><s0>Réacteur eau pressurisée</s0><s5>09</s5></fC03><fC03 i1="05" i2="X" l="ENG"><s0>Pressurized water reactor</s0><s5>09</s5></fC03><fC03 i1="05" i2="X" l="SPA"><s0>Reactor agua a presión</s0><s5>09</s5></fC03><fC03 i1="06" i2="X" l="FRE"><s0>Réacteur nucléaire</s0><s5>10</s5></fC03><fC03 i1="06" i2="X" l="ENG"><s0>Nuclear reactor</s0><s5>10</s5></fC03><fC03 i1="06" i2="X" l="SPA"><s0>Reactor nuclear</s0><s5>10</s5></fC03><fC03 i1="07" i2="X" l="FRE"><s0>Accident</s0><s5>11</s5></fC03><fC03 i1="07" i2="X" l="ENG"><s0>Accident</s0><s5>11</s5></fC03><fC03 i1="07" i2="X" l="SPA"><s0>Accidente</s0><s5>11</s5></fC03><fC03 i1="08" i2="X" l="FRE"><s0>Carbure de silicium</s0><s5>12</s5></fC03><fC03 i1="08" i2="X" l="ENG"><s0>Silicon carbide</s0><s5>12</s5></fC03><fC03 i1="08" i2="X" l="SPA"><s0>Silicio carburo</s0><s5>12</s5></fC03><fC03 i1="09" i2="X" l="FRE"><s0>Barre combustible</s0><s5>13</s5></fC03><fC03 i1="09" i2="X" l="ENG"><s0>Fuel rod</s0><s5>13</s5></fC03><fC03 i1="09" i2="X" l="SPA"><s0>Varilla combustible</s0><s5>13</s5></fC03><fC03 i1="10" i2="X" l="FRE"><s0>Dégradation</s0><s5>14</s5></fC03><fC03 i1="10" i2="X" l="ENG"><s0>Degradation</s0><s5>14</s5></fC03><fC03 i1="10" i2="X" l="SPA"><s0>Degradación</s0><s5>14</s5></fC03><fC03 i1="11" i2="X" l="FRE"><s0>Gaine (combustible)</s0><s5>16</s5></fC03><fC03 i1="11" i2="X" l="ENG"><s0>Clad</s0><s5>16</s5></fC03><fC03 i1="11" i2="X" l="SPA"><s0>Vaina (combustible)</s0><s5>16</s5></fC03><fC03 i1="12" i2="X" l="FRE"><s0>Circuit refroidissement</s0><s5>19</s5></fC03><fC03 i1="12" i2="X" l="ENG"><s0>Cooling circuit</s0><s5>19</s5></fC03><fC03 i1="12" i2="X" l="SPA"><s0>Circuito renfriamiento</s0><s5>19</s5></fC03><fC03 i1="13" i2="X" l="FRE"><s0>Modélisation</s0><s5>20</s5></fC03><fC03 i1="13" i2="X" l="ENG"><s0>Modeling</s0><s5>20</s5></fC03><fC03 i1="13" i2="X" l="SPA"><s0>Modelización</s0><s5>20</s5></fC03><fC03 i1="14" i2="X" l="FRE"><s0>Projet</s0><s5>21</s5></fC03><fC03 i1="14" i2="X" l="ENG"><s0>Project</s0><s5>21</s5></fC03><fC03 i1="14" i2="X" l="SPA"><s0>Proyecto</s0><s5>21</s5></fC03><fC03 i1="15" i2="X" l="FRE"><s0>Code calcul</s0><s5>22</s5></fC03><fC03 i1="15" i2="X" l="ENG"><s0>Computation code</s0><s5>22</s5></fC03><fC03 i1="15" i2="X" l="SPA"><s0>Código computación</s0><s5>22</s5></fC03><fC03 i1="16" i2="X" l="FRE"><s0>Rupture</s0><s5>23</s5></fC03><fC03 i1="16" i2="X" l="ENG"><s0>Rupture</s0><s5>23</s5></fC03><fC03 i1="16" i2="X" l="SPA"><s0>Ruptura</s0><s5>23</s5></fC03><fC03 i1="17" i2="X" l="FRE"><s0>Thermodynamique</s0><s5>24</s5></fC03><fC03 i1="17" i2="X" l="ENG"><s0>Thermodynamics</s0><s5>24</s5></fC03><fC03 i1="17" i2="X" l="SPA"><s0>Termodinámica</s0><s5>24</s5></fC03><fC03 i1="18" i2="X" l="FRE"><s0>Géométrie</s0><s5>25</s5></fC03><fC03 i1="18" i2="X" l="ENG"><s0>Geometry</s0><s5>25</s5></fC03><fC03 i1="18" i2="X" l="SPA"><s0>Geometría</s0><s5>25</s5></fC03><fC03 i1="19" i2="X" l="FRE"><s0>Simulateur</s0><s5>26</s5></fC03><fC03 i1="19" i2="X" l="ENG"><s0>Simulator</s0><s5>26</s5></fC03><fC03 i1="19" i2="X" l="SPA"><s0>Simulador</s0><s5>26</s5></fC03><fC03 i1="20" i2="X" l="FRE"><s0>Mesure pression</s0><s5>27</s5></fC03><fC03 i1="20" i2="X" l="ENG"><s0>Pressure measurement</s0><s5>27</s5></fC03><fC03 i1="20" i2="X" l="SPA"><s0>Medida presión</s0><s5>27</s5></fC03><fC03 i1="21" i2="X" l="FRE"><s0>Aérosol</s0><s5>29</s5></fC03><fC03 i1="21" i2="X" l="ENG"><s0>Aerosols</s0><s5>29</s5></fC03><fC03 i1="21" i2="X" l="SPA"><s0>Aerosol</s0><s5>29</s5></fC03><fN21><s1>123</s1></fN21></pA><pR><fA30 i1="01" i2="1" l="ENG"><s1>European Review Meeting on Severe Accident Research (ERMSAR)</s1><s3>Nesseber BGR</s3><s4>2008-09-23</s4></fA30></pR></standard></inist></record>Pour manipuler ce document sous Unix (Dilib)
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|texte= Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
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