Network


Latest external collaboration on country level. Dive into details by clicking on the dots.

Hotspot


Dive into the research topics where M. Große is active.

Publication


Featured researches published by M. Große.


Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance | 2008

Severe Fuel Damage Experiments With Advanced Cladding Materials to be Performed in the QUENCH Facility (QUENCH-ACM)

L. Sepold; M. Große; Martin Steinbrück; J. Stuckert

The QUENCH out-of-pile experiments are part of the Severe Fuel Damage (SFD) program at the Karlsruhe Research Center. They are to investigate the hydrogen source term that results from reflooding an uncovered core of a Light-Water Reactor (LWR) with emergency cooling water. In the QUENCH experimental program Zircaloy-4 was used as standard-type material for rod cladding and grid spacer. Up to the end of 2007, 12 QUENCH experiments have been performed with this type of cladding; two test bundles contained B4 C and one AgInCd absorber. One experiment (QUENCH-12) was conducted with Zr1%Nb cladding (VVER-type). Due to the niobium-bearing cladding, the VVER-type test QUENCH-12 could be regarded as a precursor for the upcoming program “QUENCH-ACM” with advanced cladding materials, i.e. M5, Duplex, ZIRLO, to be tested under SFD or BDBA (beyond design basis accident) conditions. These materials were developed for longer operation times in nuclear power reactors and extended burnup. They are optimized regarding their corrosion behavior under operational conditions and were also tested for LOCA (loss of coolant accident) and RIA (reactivity-initiated accident) conditions by the manufacturers. However, there are only very limited data available on the behavior of the new alloys in the SFD/BDBA temperature range, i.e. above 1500 K. The QUENCH-ACM test series has been defined with three experiments, i.e. QUENCH-14 through QUENCH-16. As in the Zircaloy-4 experiments, fuel is represented by ZrO2 pellets. Also, the test section instrumentation will be as usual with thermocouples attached to the cladding, shroud, and cooling jacket at elevations between −50 mm and 1350 mm. The QUENCH-ACM test series is scheduled to be performed in the period of 2008–2010. Test matrix and test bundle arrangements are presented in this paper.© 2008 ASME


Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security | 2014

Influence of the Temperature History on Secondary Hydriding and Mechanical Properties of Zircaloy-4 Claddings: An Analysis of the QUENCH-LOCA Bundle Tests

J. Stuckert; M. Große; C. Rössger; Martin Steinbrück; Mario Walter

Two out-of-pile bundle tests, QUENCH-L0 and QUENCH-L1, were performed recently at Karlsruhe Institute of Technology (KIT) in the framework of the QUENCH-LOCA program devoted to the investigation of the so-called secondary hydriding of the cladding. The overall objective of this bundle test series is the investigation of ballooning, burst and secondary hydrogen uptake of the cladding under representative design basis accident conditions as well as detailed post-test investigation of cladding mechanical properties to analyze the material behavior with respect to embrittlement. The program was started in 2010 with the QUENCH-L0 commissioning test using 21 electrically heated rods with as-received Zircaloy-4 claddings followed in 2012 by the QUENCH-L1 reference test using the same material. These two tests differ in 1) heat-up rate during the first transient and 2) presence of a cool-down phase before quenching. The maximum heating rate reached during QUENCH-L0 was only 2.5 K/s, whereas the transient phase of QUENCH-L1 was performed with the maximum rate of 7 K/s. The state of the QUENCH-L0 bundle was practically “frozen” immediately after the transient phase by fast injection of two-phase fluid. The reference test QUENCH-L1, was performed with a typical cooling phase after the transient phase. It provides data on Zircaloy-4 cladding embrittlement based on more prototypical temperature history. Post-test neutron radiography and tomography revealed formation of hydrogen bands around the oxidized inner cladding surface in vicinity of the burst openings for both tests. However, the concentration of hydrogen absorbed inside these bands was different for both tests: whereas the maximum hydrogen concentration for QUENCH-L0 reached 2560 wppm, the corresponding value for QUENCH-L1 was only 1690 wppm. Complementary model calculations confirm that the differences in hydrogen concentrations are mainly related to the differences in temperature sequences. Subsequent tensile tests with tube segments at room temperature revealed the dependence of the mechanical behaviour on hydrogen concentration: tubes with hydrogen contents above 1500 wppm were simultaneously double ruptured along the hydrogen bands, whereas tubes with hydrogen concentrations below 1500 wppm failed at the middle of burst openings.Copyright


Nuclear Engineering and Design | 2010

Synopsis and outcome of the QUENCH experimental program

Martin Steinbrück; M. Große; L. Sepold; J. Stuckert


Oxidation of Metals | 2011

Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C

Martin Steinbrück; N. Vér; M. Große


Annals of Nuclear Energy | 2009

Experimental and post-test calculation results of the integral reflood test QUENCH-12 with a VVER-type bundle

J. Stuckert; J. Birchley; M. Große; Timothy J. Haste; L. Sepold; Martin Steinbrück


Nuclear Engineering and Design | 2013

QUENCH-LOCA program at KIT on secondary hydriding and results of the commissioning bundle test QUENCH-L0

J. Stuckert; M. Große; C. Rössger; M. Klimenkov; Martin Steinbrück; Mario Walter


Nuclear Engineering and Design | 2011

Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO™ cladding tubes in comparison with results of previous QUENCH tests

J. Stuckert; J. Birchley; M. Große; B. Jaeckel; Martin Steinbrück


Archive | 2014

Results of the QUENCH-DEBRIS test

J. Stuckert; M. Große; Y. Onel; C. Rössger; Martin Steinbrück


MRS Proceedings | 2010

Steam and Air Oxidation Behavior of Nuclear Fuel Claddings at Severe Accident Conditions

M. Große; Martin Steinbrück; J. Stuckert


Archive | 2014

First results of the bundle test QUENCH-L4 with hydrogenated M5 claddings

J. Stuckert; M. Große; J. Moch; C. Rössger; Martin Steinbrück

Collaboration


Dive into the M. Große's collaboration.

Top Co-Authors

Avatar

Martin Steinbrück

Karlsruhe Institute of Technology

View shared research outputs
Top Co-Authors

Avatar

J. Stuckert

Karlsruhe Institute of Technology

View shared research outputs
Top Co-Authors

Avatar

C. Rössger

Karlsruhe Institute of Technology

View shared research outputs
Top Co-Authors

Avatar

L. Sepold

Karlsruhe Institute of Technology

View shared research outputs
Top Co-Authors

Avatar

Mario Walter

Karlsruhe Institute of Technology

View shared research outputs
Top Co-Authors

Avatar

M. Klimenkov

Karlsruhe Institute of Technology

View shared research outputs
Top Co-Authors

Avatar

J. Birchley

Paul Scherrer Institute

View shared research outputs
Top Co-Authors

Avatar
Top Co-Authors

Avatar

N. Vér

Hungarian Academy of Sciences

View shared research outputs
Top Co-Authors

Avatar

Zoltán Hózer

Hungarian Academy of Sciences

View shared research outputs
Researchain Logo
Decentralizing Knowledge