Separate-effect tests on zirconium cladding degradation in air ingress situations
Identifieur interne : 000092 ( PascalFrancis/Corpus ); précédent : 000091; suivant : 000093Separate-effect tests on zirconium cladding degradation in air ingress situations
Auteurs : C. Duriez ; M. Steinbrück ; D. Ohai ; T. Meleg ; J. Birchley ; T. HasteSource :
- Nuclear engineering and design [ 0029-5493 ] ; 2009.
Descripteurs français
- Pascal (Inist)
- Zirconium alliage, Gaine (combustible), Réacteur nucléaire, Combustible irradié, Probabilité, Accident, Barre combustible, Haute température, Vapeur eau, Oxydation, Nitrure, Azote, Zircaloy, Réacteur eau pressurisée, Réacteur modéré eau, Réacteur eau lourde, Tube, Thermogravimétrie, Spectrométrie masse, Inspection, Oxyde, Modélisation, Dispositif CANDU.
English descriptors
- KwdEn :
- Accident, Clad, Fuel rod, Heavy water reactor, High temperature, Inspection, Irradiated nuclear fuel, Mass spectrometry, Modeling, Nitrides, Nitrogen, Nuclear reactor, Oxidation, Oxides, Pressurized water reactor, Probability, Thermogravimetry, Tube, Water moderated reactor, Water vapor, Zircaloy, Zirconium alloy.
Abstract
In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel rods will be exposed to air-containing atmospheres at high temperatures. In comparison with steam, the presence of air is expected to result in a more rapid escalation of the accident. A state-of-the-art review performed before SARNET started showed that the existing data on zirconium alloy oxidation in air were scarce. Moreover, the exact role of zirconium nitride on the cladding degradation process was poorly understood. Regarding the cladding behaviour in air+steam or nitrogen-enriched atmospheres (encountered in oxygen-starved conditions), almost no data were available. New experimental programmes comprising small-scale tests have therefore been launched at FZK,IRSN (MOZART programme in the frame of the International Source Term Program-ISTP) and INR. Zircaloy-4 cladding in PWR (FZK, IRSN) and in CANDU (INR) geometry are investigated. On-line kinetic data are obtained on centimetre size tube segments, by thermogravimetry (FZK, IRSN and INR) or by mass spectrometry (FZK). Plugged tubes 15 cm long (FZK) are also investigated. The samples are air-oxidised either in the "as-received" state, or after pre-oxidation in steam. "Analytical" tests at constant temperature and gas composition provide basic kinetic data, while more prototypical temperature transients and sequential gas compositions are also investigated. The temperature domains extend from 600 °C up to 1500 °C. Systematic post-test metallographic inspections are performed. The paper gives a synthesis of the results obtained, comparing them in terms of kinetics and oxide scale structure and composition. A comparative analysis is performed with results of the QUENCH-10 (Q-10) bundle test, which included an air ingress phase. It is shown how the data contribute to a better understanding of the cladding degradation process, especially regarding the role of nitrogen. For modelling of the oxide scale degradation under air exposure, important features that have to be taken into account are highlighted.
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Pour connaître la documentation sur le format Inist Standard.
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Format Inist (serveur)
| NO : | PASCAL 09-0098245 INIST |
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| ET : | Separate-effect tests on zirconium cladding degradation in air ingress situations |
| AU : | DURIEZ (C.); STEINBRÜCK (M.); OHAI (D.); MELEG (T.); BIRCHLEY (J.); HASTE (T.) |
| AF : | Institut de Radioprotection et de Sûreté Nucléaire. IgSN. Direction de Prévention des Accidents Majeurs, Centre de Cadarache/13115 St Paul LezDurance/France (1 aut.); Forschungszentrum Karlsruhe, FZK, Institut für Materialforschung, Postfach 3640/76021 Karlsruhe/Allemagne (2 aut.); Institute for Nuclear Research, INR, Nuclear Material and Corrosion Department/Pitesti, 115400 Mioveni Arges/Roumanie (3 aut., 4 aut.); Paul Scherrer Institute/5232 Villigen/Suisse (5 aut., 6 aut.) |
| DT : | Publication en série; Niveau analytique |
| SO : | Nuclear engineering and design; ISSN 0029-5493; Coden NEDEAU; Pays-Bas; Da. 2009; Vol. 239; No. 2; Pp. 244-253; Bibl. 1/2 p. |
| LA : | Anglais |
| EA : | In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel rods will be exposed to air-containing atmospheres at high temperatures. In comparison with steam, the presence of air is expected to result in a more rapid escalation of the accident. A state-of-the-art review performed before SARNET started showed that the existing data on zirconium alloy oxidation in air were scarce. Moreover, the exact role of zirconium nitride on the cladding degradation process was poorly understood. Regarding the cladding behaviour in air+steam or nitrogen-enriched atmospheres (encountered in oxygen-starved conditions), almost no data were available. New experimental programmes comprising small-scale tests have therefore been launched at FZK,IRSN (MOZART programme in the frame of the International Source Term Program-ISTP) and INR. Zircaloy-4 cladding in PWR (FZK, IRSN) and in CANDU (INR) geometry are investigated. On-line kinetic data are obtained on centimetre size tube segments, by thermogravimetry (FZK, IRSN and INR) or by mass spectrometry (FZK). Plugged tubes 15 cm long (FZK) are also investigated. The samples are air-oxidised either in the "as-received" state, or after pre-oxidation in steam. "Analytical" tests at constant temperature and gas composition provide basic kinetic data, while more prototypical temperature transients and sequential gas compositions are also investigated. The temperature domains extend from 600 °C up to 1500 °C. Systematic post-test metallographic inspections are performed. The paper gives a synthesis of the results obtained, comparing them in terms of kinetics and oxide scale structure and composition. A comparative analysis is performed with results of the QUENCH-10 (Q-10) bundle test, which included an air ingress phase. It is shown how the data contribute to a better understanding of the cladding degradation process, especially regarding the role of nitrogen. For modelling of the oxide scale degradation under air exposure, important features that have to be taken into account are highlighted. |
| CC : | 001D06D04D; 001D06B04C; 001D06D04E; 230 |
| FD : | Zirconium alliage; Gaine (combustible); Réacteur nucléaire; Combustible irradié; Probabilité; Accident; Barre combustible; Haute température; Vapeur eau; Oxydation; Nitrure; Azote; Zircaloy; Réacteur eau pressurisée; Réacteur modéré eau; Réacteur eau lourde; Tube; Thermogravimétrie; Spectrométrie masse; Inspection; Oxyde; Modélisation; Dispositif CANDU |
| ED : | Zirconium alloy; Clad; Nuclear reactor; Irradiated nuclear fuel; Probability; Accident; Fuel rod; High temperature; Water vapor; Oxidation; Nitrides; Nitrogen; Zircaloy; Pressurized water reactor; Water moderated reactor; Heavy water reactor; Tube; Thermogravimetry; Mass spectrometry; Inspection; Oxides; Modeling |
| SD : | Zirconio aleación; Vaina (combustible); Reactor nuclear; Combustible irradiado; Probabilidad; Accidente; Varilla combustible; Alta temperatura; Vapor agua; Oxidación; Nitruro; Nitrógeno; Zirconio aleación; Reactor agua a presión; Reactor moderado agua; Reactor agua pesada; Tubo; Termogravimetría; Espectrometría masa; Inspección; Óxido; Modelización |
| LO : | INIST-12262.354000184170980070 |
| ID : | 09-0098245 |
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In comparison with steam, the presence of air is expected to result in a more rapid escalation of the accident. A state-of-the-art review performed before SARNET started showed that the existing data on zirconium alloy oxidation in air were scarce. Moreover, the exact role of zirconium nitride on the cladding degradation process was poorly understood. Regarding the cladding behaviour in air+steam or nitrogen-enriched atmospheres (encountered in oxygen-starved conditions), almost no data were available. New experimental programmes comprising small-scale tests have therefore been launched at FZK,IRSN (MOZART programme in the frame of the International Source Term Program-ISTP) and INR. Zircaloy-4 cladding in PWR (FZK, IRSN) and in CANDU (INR) geometry are investigated. On-line kinetic data are obtained on centimetre size tube segments, by thermogravimetry (FZK, IRSN and INR) or by mass spectrometry (FZK). Plugged tubes 15 cm long (FZK) are also investigated. The samples are air-oxidised either in the "as-received" state, or after pre-oxidation in steam. "Analytical" tests at constant temperature and gas composition provide basic kinetic data, while more prototypical temperature transients and sequential gas compositions are also investigated. The temperature domains extend from 600 °C up to 1500 °C. Systematic post-test metallographic inspections are performed. The paper gives a synthesis of the results obtained, comparing them in terms of kinetics and oxide scale structure and composition. A comparative analysis is performed with results of the QUENCH-10 (Q-10) bundle test, which included an air ingress phase. It is shown how the data contribute to a better understanding of the cladding degradation process, especially regarding the role of nitrogen. For modelling of the oxide scale degradation under air exposure, important features that have to be taken into account are highlighted.</div></front></TEI><inist><standard h6="B"><pA><fA01 i1="01" i2="1"><s0>0029-5493</s0></fA01><fA02 i1="01"><s0>NEDEAU</s0></fA02><fA03 i2="1"><s0>Nucl. eng. des.</s0></fA03><fA05><s2>239</s2></fA05><fA06><s2>2</s2></fA06><fA08 i1="01" i2="1" l="ENG"><s1>Separate-effect tests on zirconium cladding degradation in air ingress situations</s1></fA08><fA11 i1="01" i2="1"><s1>DURIEZ (C.)</s1></fA11><fA11 i1="02" i2="1"><s1>STEINBRÜCK (M.)</s1></fA11><fA11 i1="03" i2="1"><s1>OHAI (D.)</s1></fA11><fA11 i1="04" i2="1"><s1>MELEG (T.)</s1></fA11><fA11 i1="05" i2="1"><s1>BIRCHLEY (J.)</s1></fA11><fA11 i1="06" i2="1"><s1>HASTE (T.)</s1></fA11><fA14 i1="01"><s1>Institut de Radioprotection et de Sûreté Nucléaire. IgSN. 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All rights reserved.</s1></fA44><fA45><s0>1/2 p.</s0></fA45><fA47 i1="01" i2="1"><s0>09-0098245</s0></fA47><fA60><s1>P</s1></fA60><fA61><s0>A</s0></fA61><fA64 i1="01" i2="1"><s0>Nuclear engineering and design</s0></fA64><fA66 i1="01"><s0>NLD</s0></fA66><fC01 i1="01" l="ENG"><s0>In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel rods will be exposed to air-containing atmospheres at high temperatures. In comparison with steam, the presence of air is expected to result in a more rapid escalation of the accident. A state-of-the-art review performed before SARNET started showed that the existing data on zirconium alloy oxidation in air were scarce. Moreover, the exact role of zirconium nitride on the cladding degradation process was poorly understood. Regarding the cladding behaviour in air+steam or nitrogen-enriched atmospheres (encountered in oxygen-starved conditions), almost no data were available. New experimental programmes comprising small-scale tests have therefore been launched at FZK,IRSN (MOZART programme in the frame of the International Source Term Program-ISTP) and INR. Zircaloy-4 cladding in PWR (FZK, IRSN) and in CANDU (INR) geometry are investigated. On-line kinetic data are obtained on centimetre size tube segments, by thermogravimetry (FZK, IRSN and INR) or by mass spectrometry (FZK). Plugged tubes 15 cm long (FZK) are also investigated. The samples are air-oxidised either in the "as-received" state, or after pre-oxidation in steam. "Analytical" tests at constant temperature and gas composition provide basic kinetic data, while more prototypical temperature transients and sequential gas compositions are also investigated. The temperature domains extend from 600 °C up to 1500 °C. Systematic post-test metallographic inspections are performed. The paper gives a synthesis of the results obtained, comparing them in terms of kinetics and oxide scale structure and composition. A comparative analysis is performed with results of the QUENCH-10 (Q-10) bundle test, which included an air ingress phase. It is shown how the data contribute to a better understanding of the cladding degradation process, especially regarding the role of nitrogen. For modelling of the oxide scale degradation under air exposure, important features that have to be taken into account are highlighted.</s0></fC01><fC02 i1="01" i2="X"><s0>001D06D04D</s0></fC02><fC02 i1="02" i2="X"><s0>001D06B04C</s0></fC02><fC02 i1="03" i2="X"><s0>001D06D04E</s0></fC02><fC02 i1="04" i2="X"><s0>230</s0></fC02><fC03 i1="01" i2="X" l="FRE"><s0>Zirconium alliage</s0><s5>01</s5></fC03><fC03 i1="01" i2="X" l="ENG"><s0>Zirconium alloy</s0><s5>01</s5></fC03><fC03 i1="01" i2="X" l="SPA"><s0>Zirconio aleación</s0><s5>01</s5></fC03><fC03 i1="02" i2="X" l="FRE"><s0>Gaine (combustible)</s0><s5>02</s5></fC03><fC03 i1="02" i2="X" l="ENG"><s0>Clad</s0><s5>02</s5></fC03><fC03 i1="02" i2="X" l="SPA"><s0>Vaina (combustible)</s0><s5>02</s5></fC03><fC03 i1="03" i2="X" l="FRE"><s0>Réacteur nucléaire</s0><s5>03</s5></fC03><fC03 i1="03" i2="X" l="ENG"><s0>Nuclear reactor</s0><s5>03</s5></fC03><fC03 i1="03" i2="X" l="SPA"><s0>Reactor nuclear</s0><s5>03</s5></fC03><fC03 i1="04" i2="X" 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l="ENG"><s0>Zircaloy</s0><s5>13</s5></fC03><fC03 i1="13" i2="X" l="SPA"><s0>Zirconio aleación</s0><s5>13</s5></fC03><fC03 i1="14" i2="X" l="FRE"><s0>Réacteur eau pressurisée</s0><s5>14</s5></fC03><fC03 i1="14" i2="X" l="ENG"><s0>Pressurized water reactor</s0><s5>14</s5></fC03><fC03 i1="14" i2="X" l="SPA"><s0>Reactor agua a presión</s0><s5>14</s5></fC03><fC03 i1="15" i2="X" l="FRE"><s0>Réacteur modéré eau</s0><s5>15</s5></fC03><fC03 i1="15" i2="X" l="ENG"><s0>Water moderated reactor</s0><s5>15</s5></fC03><fC03 i1="15" i2="X" l="SPA"><s0>Reactor moderado agua</s0><s5>15</s5></fC03><fC03 i1="16" i2="X" l="FRE"><s0>Réacteur eau lourde</s0><s5>16</s5></fC03><fC03 i1="16" i2="X" l="ENG"><s0>Heavy water reactor</s0><s5>16</s5></fC03><fC03 i1="16" i2="X" l="SPA"><s0>Reactor agua pesada</s0><s5>16</s5></fC03><fC03 i1="17" i2="X" l="FRE"><s0>Tube</s0><s5>17</s5></fC03><fC03 i1="17" i2="X" l="ENG"><s0>Tube</s0><s5>17</s5></fC03><fC03 i1="17" i2="X" l="SPA"><s0>Tubo</s0><s5>17</s5></fC03><fC03 i1="18" i2="X" l="FRE"><s0>Thermogravimétrie</s0><s5>18</s5></fC03><fC03 i1="18" i2="X" l="ENG"><s0>Thermogravimetry</s0><s5>18</s5></fC03><fC03 i1="18" i2="X" l="SPA"><s0>Termogravimetría</s0><s5>18</s5></fC03><fC03 i1="19" i2="X" l="FRE"><s0>Spectrométrie masse</s0><s5>19</s5></fC03><fC03 i1="19" i2="X" l="ENG"><s0>Mass spectrometry</s0><s5>19</s5></fC03><fC03 i1="19" i2="X" l="SPA"><s0>Espectrometría masa</s0><s5>19</s5></fC03><fC03 i1="20" i2="X" l="FRE"><s0>Inspection</s0><s5>20</s5></fC03><fC03 i1="20" i2="X" l="ENG"><s0>Inspection</s0><s5>20</s5></fC03><fC03 i1="20" i2="X" l="SPA"><s0>Inspección</s0><s5>20</s5></fC03><fC03 i1="21" i2="X" l="FRE"><s0>Oxyde</s0><s2>NA</s2><s5>21</s5></fC03><fC03 i1="21" i2="X" l="ENG"><s0>Oxides</s0><s2>NA</s2><s5>21</s5></fC03><fC03 i1="21" i2="X" l="SPA"><s0>Óxido</s0><s2>NA</s2><s5>21</s5></fC03><fC03 i1="22" i2="X" l="FRE"><s0>Modélisation</s0><s5>22</s5></fC03><fC03 i1="22" i2="X" l="ENG"><s0>Modeling</s0><s5>22</s5></fC03><fC03 i1="22" i2="X" l="SPA"><s0>Modelización</s0><s5>22</s5></fC03><fC03 i1="23" i2="X" l="FRE"><s0>Dispositif CANDU</s0><s4>INC</s4><s5>72</s5></fC03><fN21><s1>068</s1></fN21><fN44 i1="01"><s1>OTO</s1></fN44><fN82><s1>OTO</s1></fN82></pA></standard><server><NO>PASCAL 09-0098245 INIST</NO><ET>Separate-effect tests on zirconium cladding degradation in air ingress situations</ET><AU>DURIEZ (C.); STEINBRÜCK (M.); OHAI (D.); MELEG (T.); BIRCHLEY (J.); HASTE (T.)</AU><AF>Institut de Radioprotection et de Sûreté Nucléaire. IgSN. Direction de Prévention des Accidents Majeurs, Centre de Cadarache/13115 St Paul LezDurance/France (1 aut.); Forschungszentrum Karlsruhe, FZK, Institut für Materialforschung, Postfach 3640/76021 Karlsruhe/Allemagne (2 aut.); Institute for Nuclear Research, INR, Nuclear Material and Corrosion Department/Pitesti, 115400 Mioveni Arges/Roumanie (3 aut., 4 aut.); Paul Scherrer Institute/5232 Villigen/Suisse (5 aut., 6 aut.)</AF><DT>Publication en série; Niveau analytique</DT><SO>Nuclear engineering and design; ISSN 0029-5493; Coden NEDEAU; Pays-Bas; Da. 2009; Vol. 239; No. 2; Pp. 244-253; Bibl. 1/2 p.</SO><LA>Anglais</LA><EA>In the event of air ingress during a reactor or spent fuel pond low probability accident, the fuel rods will be exposed to air-containing atmospheres at high temperatures. In comparison with steam, the presence of air is expected to result in a more rapid escalation of the accident. A state-of-the-art review performed before SARNET started showed that the existing data on zirconium alloy oxidation in air were scarce. Moreover, the exact role of zirconium nitride on the cladding degradation process was poorly understood. Regarding the cladding behaviour in air+steam or nitrogen-enriched atmospheres (encountered in oxygen-starved conditions), almost no data were available. New experimental programmes comprising small-scale tests have therefore been launched at FZK,IRSN (MOZART programme in the frame of the International Source Term Program-ISTP) and INR. Zircaloy-4 cladding in PWR (FZK, IRSN) and in CANDU (INR) geometry are investigated. On-line kinetic data are obtained on centimetre size tube segments, by thermogravimetry (FZK, IRSN and INR) or by mass spectrometry (FZK). Plugged tubes 15 cm long (FZK) are also investigated. The samples are air-oxidised either in the "as-received" state, or after pre-oxidation in steam. "Analytical" tests at constant temperature and gas composition provide basic kinetic data, while more prototypical temperature transients and sequential gas compositions are also investigated. The temperature domains extend from 600 °C up to 1500 °C. Systematic post-test metallographic inspections are performed. The paper gives a synthesis of the results obtained, comparing them in terms of kinetics and oxide scale structure and composition. A comparative analysis is performed with results of the QUENCH-10 (Q-10) bundle test, which included an air ingress phase. It is shown how the data contribute to a better understanding of the cladding degradation process, especially regarding the role of nitrogen. For modelling of the oxide scale degradation under air exposure, important features that have to be taken into account are highlighted.</EA><CC>001D06D04D; 001D06B04C; 001D06D04E; 230</CC><FD>Zirconium alliage; Gaine (combustible); Réacteur nucléaire; Combustible irradié; Probabilité; Accident; Barre combustible; Haute température; Vapeur eau; Oxydation; Nitrure; Azote; Zircaloy; Réacteur eau pressurisée; Réacteur modéré eau; Réacteur eau lourde; Tube; Thermogravimétrie; Spectrométrie masse; Inspection; Oxyde; Modélisation; Dispositif CANDU</FD><ED>Zirconium alloy; Clad; Nuclear reactor; Irradiated nuclear fuel; Probability; Accident; Fuel rod; High temperature; Water vapor; Oxidation; Nitrides; Nitrogen; Zircaloy; Pressurized water reactor; Water moderated reactor; Heavy water reactor; Tube; Thermogravimetry; Mass spectrometry; Inspection; Oxides; Modeling</ED><SD>Zirconio aleación; Vaina (combustible); Reactor nuclear; Combustible irradiado; Probabilidad; Accidente; Varilla combustible; Alta temperatura; Vapor agua; Oxidación; Nitruro; Nitrógeno; Zirconio aleación; Reactor agua a presión; Reactor moderado agua; Reactor agua pesada; Tubo; Termogravimetría; Espectrometría masa; Inspección; Óxido; Modelización</SD><LO>INIST-12262.354000184170980070</LO><ID>09-0098245</ID></server></inist></record>Pour manipuler ce document sous Unix (Dilib)
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