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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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 environment Measured 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
Show/Hide Additional Details ▼ 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
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