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Buxton, L.D.; Nelson, L.S.; Benedick, W.B.
Proceedings of the fourth CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety - Volumes 2+31979
Proceedings of the fourth CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety - Volumes 2+31979
AbstractAbstract
[en] When the (US) Reactor Safety Study on the assessment of accident risks in light water reactors (LWR) was performed, it was noted that much of the basic data required to realistically evaluate the probability of occurrence of containment breaching steam explosions did not exist. Consequently, the U. S. Nuclear Regulatory Commission (Fuel Behavior Research Branch, Division of Reactor Safety Research) initiated a program at Sandia Laboratories to provide relevant data on the interaction of molten LWR core materials with water. Two different sub-tasks were established to achieve this goal. The first was the performance of laboratory-scale experiments to investigate the ability to trigger steam explosions for realistic LWR core melt simulants under a wide range of initial conditions. The second was the performance of field-scale experiments to investigate the efficiency of converting the thermal energy of the melt into mechanical work in much larger steam explosions. Both types of experiments and their conclusions are reviewed
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Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, Committee on the safety of nuclear installations - OECD/NEA/CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France); 493 p; Oct 1979; p. 68-89; 4. CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety; Bournemouth (United Kingdom); 2-5 Apr 1979; 8 refs.
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