Organization / Localization: FZK
Country: Germany
Test Identification: 10
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 23/2 Ag/In/Cd Ar/Steam 0.2/0.4 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP20
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 12
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 23/2 Ag/In/Cd Ar/Steam 0.2/0.3 Quench by water ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP8
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 13
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 23/2 Ag/In/Cd Ar/Steam 0.2/0.4 Quench by water ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP15
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 15
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 23/2 Ag/In/Cd Ar/Steam 0.2/6.0 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP10
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 16
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 18/B4C blade Ar/Steam 0.2/0.6 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP9
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 17
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 18/B4C blade Ar/Steam 0.2/0.5 Quench by water ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP11
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 18
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 48/B4C blade Ar/Steam 0.2/0.6 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP14
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 2
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 25/0 Ar/Steam 0.2/0.7 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP5
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 28
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 18/B4C blade Ar/Steam 0.2/0.4 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP19
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 29
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 23/2 Ag/In/Cd Ar/Steam 0.2/0.4 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP16
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 3
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 25/0 Ar/Steam 0.2/0.5 Slow cooling in Ar ≈ 2400°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP6
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 30
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 23/2 Ag/In/Cd Ar/Steam 0.2/0.4 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP18
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 31
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 18/B4C blade Ar/Steam 0.2/0.4 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP17
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 33
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 18/B4C blade Ar/Steam (trace) 0.2/0.5 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP21
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 5
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 24/1 Ag/In/Cd Ar/Steam 0.2/0.4 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP7
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 7
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 52/5 Ag/In/Cd Ar/Steam 0.2/0.5 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP13
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: 9
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 23/2 Ag/In/Cd Ar/Steam 1.0/0.2 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP12
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: W1
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 19 VVER Ar/Steam 0.2/0.35 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP22
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked
Organization / Localization: FZK
Country: Germany
Test Identification: W2
SA-Related Topics / Phenomena: Early phases of core degradation in light water reactor systems (PWR and BWR) in a bundle environmentMeasured Parameters: 18 VVER/1 B4C rod Ar/Steam 0.2/0.3 Slow cooling in Ar ≈ 2000°C
Simulation Code: ATHLET-CD, ICARE2, KESS-III, MELCOR, RAPTA and SCDAP/RELAP23
References: Schanz, G., Hagen, S., Hofmann, P., Schumacher, G., Sepold, L., 1992. Information onthe evolution of severe LWR fuel element damage obtained in the CORA program.J. Nucl. Mater. 188, 131–145. Hofmann, P., Hagen, S., Noack, V., Schanz, G., Sepold, L., 1997. Chemical–physicalbehaviour of light water reactor core components tested under severe reactoraccident conditions in the CORA facility. Nucl. Technol. 118, 200–224. Trambauer, K., Haste, T., Adroguer, B., Hózer, Z., Magallon, D., Zurita, A., October2000. In-Vessel Core Degradation Code Validation Matrix: Update 1996–1999.OECD/NEA/CSNI/R(2000)21.
IP/Copyright Situation: To be Checked