Search Results - "Tromm, W"
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1
Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention
Published in Nuclear engineering and design (01-02-2018)“…•Simple equations for temperature gradients in liquid-solid systems are given.•The models are compared with data from METCOR, METCOR-P, MASCA projects.•A model…”
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Journal Article -
2
Ranking of severe accident research priorities
Published in Progress in nuclear energy (New series) (2010)“…The objectives of the SARNET network are to define common research programmes in the field of severe accidents and to develop common computer tools and…”
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Journal Article Conference Proceeding -
3
Oxidation kinetics of corium pool
Published in Nuclear engineering and design (01-09-2013)“…•The analysis of experimental data on molten corium oxidation was been carried out.•The analysis has revealed the main factors influencing the oxidation…”
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4
Phase diagram of the UO2–FeO1+x system
Published in Journal of nuclear materials (15-05-2007)“…Phase-relation studies of the UO2-FeO1+x system in an inert atmosphere are presented. The eutectic point has been determined, which corresponds to a…”
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Journal Article -
5
Phase diagram of the ZrO2–FeO system
Published in Journal of nuclear materials (01-01-2006)“…The results on the ZrO2-FeO system studies in a neutral atmosphere are presented. The refined eutectic point has been found to correspond to a ZrO2…”
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Journal Article -
6
VVER vessel steel corrosion at interaction with molten corium in oxidizing atmosphere
Published in Nuclear engineering and design (01-06-2009)“…The long-term in-vessel corium retention (IVR) in the lower head bears a risk of the vessel wall deterioration caused by steel corrosion. The ISTC METCOR…”
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Journal Article -
7
Corrosion of vessel steel during its interaction with molten corium
Published in Nuclear engineering and design (01-09-2006)“…This paper is concerned with corrosion of a cooled vessel steel structure interacting with molten corium in air and neutral (nitrogen) atmospheres during an…”
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Journal Article -
8
Corrosion of vessel steel during its interaction with molten corium
Published in Nuclear engineering and design (01-07-2006)“…An experimental examination of the cooled vessel steel corrosion during the interaction with molten corium is presented. The experiments have been conducted on…”
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Journal Article -
9
Corium spreading and coolability: CSC Project
Published in Nuclear engineering and design (01-11-2001)“…In the context of severe accidents, large R&D efforts throughout the world are currently directed towards ex-vessel corium behaviour. Among the mitigation…”
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Journal Article Conference Proceeding -
10
KIT reactor safety research for LWRs: Research lines, numerical tools, and prospects
Published in Nuclear engineering and design (01-12-2023)“…•Unique computational routes for safety assessment and radiological risk estimation.•High-fidelity coupled tools based on Monte Carlo with static and dynamic…”
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Journal Article -
11
Experiments for a core catcher concept based on water addition from below
Published in Nuclear engineering and design (01-08-1995)“…A core catcher concept is proposed to be integrated into a new PWR design based on the standard German PWR. The core catcher achieves coolability by spreading…”
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Journal Article -
12
Controlling and cooling core melts outside the pressure vessel
Published in Nuclear engineering and design (01-12-2000)“…For future reactors, the control and cooling of ex-vessel corium melts is under consideration to increase the passive safety features even for very unlikely…”
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13
Concept of a core cooling system and experiments performed
Published in Nuclear engineering and design (1995)“…One of the problems which must be solved in severe accidents is the melt-concrete interaction which does occur when the core debris penetrates the lower…”
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Journal Article -
14
BETA experiments on melt-concrete interaction: the role of zirconium and the potential sump water contact during core melt-down accidents
Published in Nuclear engineering and design (01-02-1995)“…In the BETA test facility of Kernforschungszentrum Karlsruhe, prototypical core melts can be simulated in concrete structures sufficient in size to allow a…”
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Journal Article -
15
Corrosion of vessel steel during its interaction with molten corium: Part 1. Experimental
Published in Nuclear engineering and design (01-09-2006)“…This paper is concerned with corrosion of a cooled vessel steel structure interacting with molten corium in air and neutral (nitrogen) atmospheresduring an…”
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Journal Article -
16
Corrosion of vessel steel during its interaction with molten corium: Part 2. Model development
Published in Nuclear engineering and design (01-07-2006)“…An experimental examination of the cooled vessel steel corrosion during the interaction with molten corium is presented. The experiments havebeen conducted on…”
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Journal Article -
17
Phase diagram of the UO 2–FeO 1+ x system
Published in Journal of nuclear materials (2007)“…Phase-relation studies of the UO 2–FeO 1+ x system in an inert atmosphere are presented. The eutectic point has been determined, which corresponds to a…”
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Journal Article -
18
Phase diagram of the ZrO 2–FeO system
Published in Journal of nuclear materials (2006)“…The results on the ZrO 2–FeO system studies in a neutral atmosphere are presented. The refined eutectic point has been found to correspond to a ZrO 2…”
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Journal Article -
19
Phase transformation in the binary section of the UO2-FeO-Fe system
Published in Radiochemistry (New York, N.Y.) (01-02-2007)Get full text
Journal Article -
20
Phase transformation in the binary section of the UO 2 -FeO-Fe system
Published in Radiochemistry (New York, N.Y.) (2007)“…Phase transformations in the oxide binary section of the UO 2 -FeO-Fe ternary system were studied. The melting onset point of the UO 2 -FeO heterogeneous…”
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