Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments

Interactions in Zircaloy/UO_2 fuel rod bundles with Inconel spacers at temperatures above 1200deg C (posttest results of severe fuel damage experiments CORA-2 and CORA-3)

Sepold, L.
Schanz, G.
Hofmann, P.
Hagen, S.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Hauptabteilung Ingenieurtechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheitsforschung
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Material- und Festkoerperforschung

January 1990

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...

Transient deformation properties of Zircaloy for LOCA simulation. Final report

Hann, C. R.
Mohr, C. L.
Busness, K. M.
Olson, N. J.
Reich, F. R.
Stewart, K. B.

May 1980

This experimental data report is Volume 4 of a series of 5 volumes describing the oxidation and defo...

Study of zircaloy-4 cladding air degradation at high temperature

Lasserre, Marina
Coindreau, Olivia
Pijolat, Michèle
Peres, Véronique
Mermoux, Michel
Mardon, Jean Paul

July 2013

Prix de la Meilleure Communication EuropéenneInternational audienceZircaloy cladding, providing the ...

Pre-oxidised BWR test CORA-28: Test results

Schumacher, G.
Schanz, G.
Sepold, L.
Noack, V.
Hagen, S.
Hofmann, P.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Hauptabteilung Ingenieurtechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung

January 1997

The CORA out-of-pile experiments were part of the international Severe Fuel Damage (SFD) program. Th...

Experimental characterization of Zircaloy-4 sheet deformation during combined hydriding and corrosion

Krebs, B.
Desquines, J.
Busser, V.
Drouan, D.
Zanellato, O.

April 2013

International audienceIn the frame of its research activity on nuclear fuel safety, the French "Inst...

Oxidation Behavior of Zr-Alloy Cladding Candidates for the TrEat Reactor

Vandegrift, Jordan L.
Efaw, Corey M.
Price, Patrick M.
Butt, Darryl P.
Hurley, Michael F.
Jaques, Brian J.

January 2020

The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...

Mechanical properties of zircaloy-4 PWR fuel cladding with burnup 54-64MWd/kgU and implications for RIA behavior

Desquines, J.
Cazalis, B.
Bernaudat, C.
Poussard, C.
Averty, X.
Yvon, P.

June 2005

International audienceThe PROMETRA material testing program is a support program related to the stud...

Plastic deformation process and fracture of Zircaloy-4 PWR cladding samples tested under RIA loading conditions monitored with high speed optical and infrared cameras

Hellouin de Menibus, Arthur
Besson, Jacques
Crépin, Jérôme
Carassou, Sébastien

August 2011

The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...

Physico-chemical behavior of Zircaloy fuel rod cladding tubes during LWR severe accident reflood. Pt. 1 and 2 Pt. 1: Experimental results of single rod quench experiments. Pt. 2: Modelling of quench phenomena

Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung)
Shestak, V.E. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung)
Veshchunov, M.S. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Berdyshev, A.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Boldyrev, A.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Matweev, L.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Palagin, A.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Hofmann, P. (Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Noack, V. (Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung

January 1997

A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...

Mechanical property testing of irradiated zircaloy cladding under reactor transient conditions.

Daum, R. S.
Majumdar, S.
Tsai, H.
Bray, T. S.
Billone, M. C.
Koss, D. A.
Motta, A. T.

October 2001

Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...

Pre-oxidised PWR test CORA-29: test results

Schumacher, G.
Schanz, G.
Sepold, L.
Hagen, S.
Hofmann, P.
Noack, V.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Hauptabteilung Ingenieurtechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung

January 1997

The CORA-Out-of-pile experiments are part of the international Severe Fuel Damage (SFD) prgram. They...

Oxidation of Zirconium Alloy Fuel Cladding Material

Vandegrift, Jordan
Parga, Clemente J.
Coryell, Ben
Jaques, Brian J.

April 2019

Zirconium alloys are often used as nuclear fuel cladding. During transients the cladding may be expo...

Quench behavior of zircaloy fuel rod cladding tubes. Small-scale experiments and modeling of the quench phenomena

Hofmann, P.
Miassoedov, A.
Veshchunov, M.S. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Steinbock, L.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung)
Berdyshev, A.V.
Boldyrev, A.V.
Palagin, A.V.
Shestak, V.E.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Steinbrueck, M. (Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung

January 1999

In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...

Chemical interactions of Zircaloy-4 tubing with UO2 fuel and oxygen at temperatures between 900 and 2000 deg C (experiments and PECLOX code). Pt. 1-3 Pt. 1: Experimental results. Pt. 2: PECLOX: A computer model for the calculation of the internal and the external Zircaloy cladding oxidation. Pt. 3: Verification of the PECLOX code

Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Dept. de Materiales
Hofmann, P.
Garcia, E.A.
Neitzel, H.J.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Material- und Festkoerperforschung

January 1988

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...

A review of Zircaloy fuel cladding behavior in a loss-of-coolant accident

Erbacher, F.J.
Leistikow, S.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Material- und Festkoerperforschung
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1985

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...

Interactions in Zircaloy/UO_2 fuel rod bundles with Inconel spacers at temperatures above 1200deg C (posttest results of severe fuel damage experiments CORA-2 and CORA-3)

Sepold, L.
Schanz, G.
Hofmann, P.
Hagen, S.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Hauptabteilung Ingenieurtechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheitsforschung
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Material- und Festkoerperforschung

January 1990

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...

Transient deformation properties of Zircaloy for LOCA simulation. Final report

Hann, C. R.
Mohr, C. L.
Busness, K. M.
Olson, N. J.
Reich, F. R.
Stewart, K. B.

May 1980

This experimental data report is Volume 4 of a series of 5 volumes describing the oxidation and defo...

Study of zircaloy-4 cladding air degradation at high temperature

Lasserre, Marina
Coindreau, Olivia
Pijolat, Michèle
Peres, Véronique
Mermoux, Michel
Mardon, Jean Paul

July 2013

Prix de la Meilleure Communication EuropéenneInternational audienceZircaloy cladding, providing the ...

Pre-oxidised BWR test CORA-28: Test results

Schumacher, G.
Schanz, G.
Sepold, L.
Noack, V.
Hagen, S.
Hofmann, P.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Hauptabteilung Ingenieurtechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung

January 1997

The CORA out-of-pile experiments were part of the international Severe Fuel Damage (SFD) program. Th...

Experimental characterization of Zircaloy-4 sheet deformation during combined hydriding and corrosion

Krebs, B.
Desquines, J.
Busser, V.
Drouan, D.
Zanellato, O.

April 2013

International audienceIn the frame of its research activity on nuclear fuel safety, the French "Inst...

Oxidation Behavior of Zr-Alloy Cladding Candidates for the TrEat Reactor

Vandegrift, Jordan L.
Efaw, Corey M.
Price, Patrick M.
Butt, Darryl P.
Hurley, Michael F.
Jaques, Brian J.

January 2020

The TREAT facility, located at the Idaho National Laboratory, is an air-cooled test facility designe...

Mechanical properties of zircaloy-4 PWR fuel cladding with burnup 54-64MWd/kgU and implications for RIA behavior

Desquines, J.
Cazalis, B.
Bernaudat, C.
Poussard, C.
Averty, X.
Yvon, P.

June 2005

International audienceThe PROMETRA material testing program is a support program related to the stud...

Plastic deformation process and fracture of Zircaloy-4 PWR cladding samples tested under RIA loading conditions monitored with high speed optical and infrared cameras

Hellouin de Menibus, Arthur
Besson, Jacques
Crépin, Jérôme
Carassou, Sébastien

August 2011

The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...

Physico-chemical behavior of Zircaloy fuel rod cladding tubes during LWR severe accident reflood. Pt. 1 and 2 Pt. 1: Experimental results of single rod quench experiments. Pt. 2: Modelling of quench phenomena

Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung)
Shestak, V.E. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung)
Veshchunov, M.S. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Berdyshev, A.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Boldyrev, A.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Matweev, L.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Palagin, A.V. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Hofmann, P. (Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Noack, V. (Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung

January 1997

A series of separate-effects tests is being carried out on Zircaloy PWR fuel rod cladding to study t...

Mechanical property testing of irradiated zircaloy cladding under reactor transient conditions.

Daum, R. S.
Majumdar, S.
Tsai, H.
Bray, T. S.
Billone, M. C.
Koss, D. A.
Motta, A. T.

October 2001

Specimen geometries have been developed to determine the mechanical properties of irradiated Zircalo...

Pre-oxidised PWR test CORA-29: test results

Schumacher, G.
Schanz, G.
Sepold, L.
Hagen, S.
Hofmann, P.
Noack, V.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Hauptabteilung Ingenieurtechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung

January 1997

The CORA-Out-of-pile experiments are part of the international Severe Fuel Damage (SFD) prgram. They...

Oxidation of Zirconium Alloy Fuel Cladding Material

Vandegrift, Jordan
Parga, Clemente J.
Coryell, Ben
Jaques, Brian J.

April 2019

Zirconium alloys are often used as nuclear fuel cladding. During transients the cladding may be expo...

Quench behavior of zircaloy fuel rod cladding tubes. Small-scale experiments and modeling of the quench phenomena

Hofmann, P.
Miassoedov, A.
Veshchunov, M.S. (Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Nuclear Safety)
Steinbock, L.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung)
Berdyshev, A.V.
Boldyrev, A.V.
Palagin, A.V.
Shestak, V.E.
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Projekt Nukleare Sicherheitsforschung
Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung
Steinbrueck, M. (Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Inst. fuer Materialforschung

January 1999

In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...

Chemical interactions of Zircaloy-4 tubing with UO2 fuel and oxygen at temperatures between 900 and 2000 deg C (experiments and PECLOX code). Pt. 1-3 Pt. 1: Experimental results. Pt. 2: PECLOX: A computer model for the calculation of the internal and the external Zircaloy cladding oxidation. Pt. 3: Verification of the PECLOX code

Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Dept. de Materiales
Hofmann, P.
Garcia, E.A.
Neitzel, H.J.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Material- und Festkoerperforschung

January 1988

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...

A review of Zircaloy fuel cladding behavior in a loss-of-coolant accident

Erbacher, F.J.
Leistikow, S.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Material- und Festkoerperforschung
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1985

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...

Interactions in Zircaloy/UO_2 fuel rod bundles with Inconel spacers at temperatures above 1200deg C (posttest results of severe fuel damage experiments CORA-2 and CORA-3)

Sepold, L.
Schanz, G.
Hofmann, P.
Hagen, S.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Hauptabteilung Ingenieurtechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheitsforschung
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Material- und Festkoerperforschung

January 1990

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Kar...

Transient deformation properties of Zircaloy for LOCA simulation. Final report

Hann, C. R.
Mohr, C. L.
Busness, K. M.
Olson, N. J.
Reich, F. R.
Stewart, K. B.

May 1980

This experimental data report is Volume 4 of a series of 5 volumes describing the oxidation and defo...

Study of zircaloy-4 cladding air degradation at high temperature

Lasserre, Marina
Coindreau, Olivia
Pijolat, Michèle
Peres, Véronique
Mermoux, Michel
Mardon, Jean Paul

July 2013

Prix de la Meilleure Communication EuropéenneInternational audienceZircaloy cladding, providing the ...

Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments

Abstract

Extracted data

Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments

Abstract

Extracted data

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