Fuel rod simulator effects in flooding experiments single rod tests

Extrapolation of data from simulant-material experiments to the work potential of fuel penetrating through upper core structures in core disruptive accidents

Meyer, L.
Wilhelm, D.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Schneller Brueter

January 1985

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

Engine surge simulation in wind-tunnel model inlet ducts

Lotter, K.
Mackrodt, P.A.
Scherbaum, R.
Messerschmitt-Boelkow-Blohm G.m.b.H., Muenchen (Germany). Unternehmensbereich Hubschrauber und Flugzeuge

January 1988

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

Modelling of pellet-clad interaction during power ramp in water reactor fuel

ROZZIA, DAVIDE

October 2049

The comprehensive understanding of fuel rod behavior and accurate prediction of the lifetime in norm...

SEFLEX fuel rod simulator effects in flooding experiments. Pt. 1 Evaluation report

Ihle, P.
Rust, K.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1986

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

SEFLEX fuel rod simulator effects in flooding experiments. Pt. 3 Blocked bundle data

Rust, K.
Ihle, P.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1986

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

Numerical investigation of hydraulic ram effects in fuel tanks

Helwig, C.H.M.
Sachs, G.W.
Seidel, K.G.K. (Messerschmitt-Boelkow-Blohm G.m.b.H. (MBB), Schrobenhausen (Germany))
Messerschmitt-Boelkow-Blohm G.m.b.H. (MBB), Ottobrunn (Germany). Unternehmensbereich Apparate

January 1987

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

THIBO experiments. Experiments on thermohydraulically induced fuel rod oscillations in a sodium flow Final report

Bojarsky, E.
Schmidt, L.
Reiser, H.
Deckers, H.
Lehning, H.
Piel, D.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Materialforschung.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheitsforschung

January 1991

SIGLEAvailable from TIB Hannover: ZA 5141(4798) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - T...

Post test investigation of the single rod tests ESSI 1-11 on temperature excalation in PWR fuel rod simulators due to the Zircaloy/steam reaction

Hagen, S.
Kapulla, H.
Malauschek, H.
Katanishi, S.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Hauptabteilung Ingenieurtechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1987

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

Experimental simulation of activity release from leaking fuel rods

Barbara Somfai
Zoltán Hózer
Imre Nagy

October 2018

The Leaking Fuel Experiment test facility was designed to simulate the activity release from spent l...

Fuel Performance Modelling and Simulations: Oxide Fuel Performance Modelling and Simulation

VAN UFFELEN Paul
SUZUKI M.

February 2011

In order to ensure the safe and economic operation of fuel rods, it is necessary to be able to predi...

Simulation of nuclear fuel rod behavior in experimental facilities

D'Auria F.
Di Marco P.
Nava M.

January 1984

The document deals with the application of a numerical model, called POTEL, to determine the electri...

Zwangs- und Schwerkraftflutversuche an hexagonalen Stabbuendelgeometrien Abschlussbericht

Schmidt, H.
Just, W.
Erbacher, F.
Wiehr, K.
Harten, U.
Kernforschungszentrum Karlsruhe GmbH (Germany). Projekt Nukleare Sicherheitsforschung
Kernforschungszentrum Karlsruhe GmbH (KfK) (Germany). Inst. fuer Angewandte Thermo- und Fluiddynamik (IATF)

January 1993

This report describes reflooding experiments in two different fuel rod simulator bundles (FRSB) with...

SEVERE FUEL DAMAGE EXPERIMENTS PERFORMED IN THE QUENCH FACILITY WITH 21-ROD BUNDLES OF LWR-TYPE

J. Stuckert

January 2016

The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...

A study of different cases of VVER reactor core flooding in a large break loss of coolant accident

Yury Alekseevich Bezrukov
Vladimir Ivanovitc Schekoldin
Sergey Ivanovich Zaitsev
Andrey Nikolaevich Churkin
Evgeny Aleksandrovich Lisenkov

January 2016

The paper covers the results of VVER core reflooding studies in fuel assembly (FA) mockup of 126 fue...

Getting the details of fuel rod simulation in reactor safety analysis right: performance of the code coupling DYN3D-TRANSURANUS for RIA

HOLT Lars
ROHDE Ulrich
SEIDL Markus
SCHUBERT Arndt
VAN UFFELEN Paul
MACIAN-JUAN Rafael

March 2014

Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...

Extrapolation of data from simulant-material experiments to the work potential of fuel penetrating through upper core structures in core disruptive accidents

Meyer, L.
Wilhelm, D.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Schneller Brueter

January 1985

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

Engine surge simulation in wind-tunnel model inlet ducts

Lotter, K.
Mackrodt, P.A.
Scherbaum, R.
Messerschmitt-Boelkow-Blohm G.m.b.H., Muenchen (Germany). Unternehmensbereich Hubschrauber und Flugzeuge

January 1988

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

Modelling of pellet-clad interaction during power ramp in water reactor fuel

ROZZIA, DAVIDE

October 2049

The comprehensive understanding of fuel rod behavior and accurate prediction of the lifetime in norm...

SEFLEX fuel rod simulator effects in flooding experiments. Pt. 1 Evaluation report

Ihle, P.
Rust, K.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1986

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

SEFLEX fuel rod simulator effects in flooding experiments. Pt. 3 Blocked bundle data

Rust, K.
Ihle, P.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Reaktorbauelemente
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1986

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

Numerical investigation of hydraulic ram effects in fuel tanks

Helwig, C.H.M.
Sachs, G.W.
Seidel, K.G.K. (Messerschmitt-Boelkow-Blohm G.m.b.H. (MBB), Schrobenhausen (Germany))
Messerschmitt-Boelkow-Blohm G.m.b.H. (MBB), Ottobrunn (Germany). Unternehmensbereich Apparate

January 1987

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

THIBO experiments. Experiments on thermohydraulically induced fuel rod oscillations in a sodium flow Final report

Bojarsky, E.
Schmidt, L.
Reiser, H.
Deckers, H.
Lehning, H.
Piel, D.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Materialforschung.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheitsforschung

January 1991

SIGLEAvailable from TIB Hannover: ZA 5141(4798) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - T...

Post test investigation of the single rod tests ESSI 1-11 on temperature excalation in PWR fuel rod simulators due to the Zircaloy/steam reaction

Hagen, S.
Kapulla, H.
Malauschek, H.
Katanishi, S.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Hauptabteilung Ingenieurtechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Nukleare Sicherheit

January 1987

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

Experimental simulation of activity release from leaking fuel rods

Barbara Somfai
Zoltán Hózer
Imre Nagy

October 2018

The Leaking Fuel Experiment test facility was designed to simulate the activity release from spent l...

Fuel Performance Modelling and Simulations: Oxide Fuel Performance Modelling and Simulation

VAN UFFELEN Paul
SUZUKI M.

February 2011

In order to ensure the safe and economic operation of fuel rods, it is necessary to be able to predi...

Simulation of nuclear fuel rod behavior in experimental facilities

D'Auria F.
Di Marco P.
Nava M.

January 1984

The document deals with the application of a numerical model, called POTEL, to determine the electri...

Zwangs- und Schwerkraftflutversuche an hexagonalen Stabbuendelgeometrien Abschlussbericht

Schmidt, H.
Just, W.
Erbacher, F.
Wiehr, K.
Harten, U.
Kernforschungszentrum Karlsruhe GmbH (Germany). Projekt Nukleare Sicherheitsforschung
Kernforschungszentrum Karlsruhe GmbH (KfK) (Germany). Inst. fuer Angewandte Thermo- und Fluiddynamik (IATF)

January 1993

This report describes reflooding experiments in two different fuel rod simulator bundles (FRSB) with...

SEVERE FUEL DAMAGE EXPERIMENTS PERFORMED IN THE QUENCH FACILITY WITH 21-ROD BUNDLES OF LWR-TYPE

J. Stuckert

January 2016

The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...

A study of different cases of VVER reactor core flooding in a large break loss of coolant accident

Yury Alekseevich Bezrukov
Vladimir Ivanovitc Schekoldin
Sergey Ivanovich Zaitsev
Andrey Nikolaevich Churkin
Evgeny Aleksandrovich Lisenkov

January 2016

The paper covers the results of VVER core reflooding studies in fuel assembly (FA) mockup of 126 fue...

Getting the details of fuel rod simulation in reactor safety analysis right: performance of the code coupling DYN3D-TRANSURANUS for RIA

HOLT Lars
ROHDE Ulrich
SEIDL Markus
SCHUBERT Arndt
VAN UFFELEN Paul
MACIAN-JUAN Rafael

March 2014

Over the last decades the importance of fuel-specific processes for safety analysis has grown, due t...

Extrapolation of data from simulant-material experiments to the work potential of fuel penetrating through upper core structures in core disruptive accidents

Meyer, L.
Wilhelm, D.
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Inst. fuer Neutronenphysik und Reaktortechnik
Kernforschungszentrum Karlsruhe G.m.b.H. (KfK) (Germany). Projekt Schneller Brueter

January 1985

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

Engine surge simulation in wind-tunnel model inlet ducts

Lotter, K.
Mackrodt, P.A.
Scherbaum, R.
Messerschmitt-Boelkow-Blohm G.m.b.H., Muenchen (Germany). Unternehmensbereich Hubschrauber und Flugzeuge

January 1988

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

Modelling of pellet-clad interaction during power ramp in water reactor fuel

ROZZIA, DAVIDE

October 2049

The comprehensive understanding of fuel rod behavior and accurate prediction of the lifetime in norm...

Fuel rod simulator effects in flooding experiments single rod tests

Abstract

Extracted data

Fuel rod simulator effects in flooding experiments single rod tests

Abstract

Extracted data

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