Solidus and liquidus temperatures of core-concrete mixtures
- Argonne National Lab., IL (United States)
Solidus and liquidus temperatures were measured for four types of concrete (limestone, limestone sand, basalt, and siliceous) and for their mixtures with urania and zirconia. Differential thermal analysis (DTA) was generally employed to determine the solidus and liquidus temperatures. However, some liquidus temperatures were also measured by rotational viscometry. The measured solidus temperatures for the urania-zirconia-concrete mixtures were significantly lower (hundreds of degrees) than those employed in the CORCON-Mod 2 thermal hydraulic code, and the measured liquidus temperatures were significantly higher (also hundreds of degrees). The liquidus temperatures for urania-zirconia-concrete mixtures containing limestone or limestone-sand concrete were generally above 2850 K, which was the upper temperature limit of our experiments. The revised solidus and liquidus temperatures are to be incorporated in the CORCON-Mod 3 thermal hydraulic code which is an integral part of the US Nuclear Regulatory Commission's NELCOR Code. MELCOR computes the consequences of severe accidents at nuclear reactors. DTA was also employed to redetermine the calcia-urania (CaO-UO[sub 2]) phase diagram. Earlier data were not in agreement, and this binary phase diagram is required in computer programs that calculate the phase diagrams (and solidus and liquidus temperatures) of urania-zirconia-concrete systems from the phase diagrams of simpler systems. A eutectic temperature and composition of 2218[plus minus]5 K and 37 mol% U0[sub 2], respectively, were determined for the CaO-U0[sub 2] system. The solubility of CaO in U0[sub 2] at the eutectic temperature was 30 mot% CaO.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 7368747
- Report Number(s):
- NUREG/CR-6032; ANL-93/9; ON: TI93016060
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
CONCRETES
INTERACTIONS
CORIUM
WATER COOLED REACTORS
REACTOR ACCIDENTS
MIXTURES
PHASE STUDIES
PHASE TRANSFORMATIONS
TEMPERATURE DISTRIBUTION
THERMAL ANALYSIS
THERMODYNAMICS
URANIUM OXIDES
ZIRCONIUM OXIDES
ACCIDENTS
ACTINIDE COMPOUNDS
BUILDING MATERIALS
CHALCOGENIDES
DISPERSIONS
MATERIALS
OXIDES
OXYGEN COMPOUNDS
REACTORS
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
ZIRCONIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
360102 - Metals & Alloys- Structure & Phase Studies
360602 - Other Materials- Structure & Phase Studies
220200 - Nuclear Reactor Technology- Components & Accessories