Results 201 to 210 of about 848 (238)

A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident

Kerntechnik, 2017
Abstract For calculation of the radiological consequences of Large Break Loss of Coolant (LBLOCA) events, a set of various computer codes modeling the corresponding physical processes, disciplines and their appropriate subsequent data exchange are necessary. For demonstrating the methodology applied in MTA EK, a LBLOCA event at shut down
A. Keresztúri, Á. Brolly, I. Panka, T. Pázmándi, I. Trosztel   +4 more
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RADIOACTIVITY CONFINEMENT FOR LOSS OF COOLANT ACCIDENTS IN NET

1993
This paper provides an overview of confinement pressurization for the case of Loss of Coolant Accidents (LOCAs) occurring during plasma burn as well as during conditioning and baking. The radioactivity confinement strategy is outlined.
Edgar Ebert, Friedrich Fauser, Markus Iseli   +2 more
openaire   +1 more source

Loss-of-vacuum, loss-of-coolant, and loss-of-flow accident analysis for NET ITER

1990
Analyses are presented οη hypothetical accidents in NET/ITER involving: -air ingress in the graphite-coated plasma chamber through a breach in the vacuum vessel (LOVA); -loss-of-coolant inside the vacuum vessel with water ingress in the plasma chamber (inside LOCA); -loss-of-coolant outside the vacuum vessel (outside LOCA); -loss-of-power with the ...
Andritsos, F., Caouris, Y. G., Rocco, P., ZUCCHETTI, MASSIMO, Klippel, H. T., Komen, E., Boogaard, J. P. A., van den Zylberstejn, T., Drimille, E., Mazille, F.   +9 more
openaire   +2 more sources

Theoretical study on loss of coolant accident of a research reactor

Nuclear Engineering and Design, 2016
Abstract Under the design conditions of a research reactor, the siphon phenomenon induced by pipe rupture can cause continuous efflux of water. In order to prevent water efflux, an additional facility is necessary. A siphon breaker is a type of safety facility that can resist the loss of coolant effectively.
Kwon-Yeong Lee, Wan-Soo Kim
openaire   +1 more source

Identification of Loss-of-Coolant Accidents in LWRs by Inverse Models

Nuclear Technology, 2004
This paper describes a novel diagnostic method based on inverse models that could be applied to identification of transients and accidents in nuclear power plants. In particular, it is shown that such models could be successfully applied to identification of loss-of-coolant accidents (LOCAs).
Wojciech Cholewa, Wiktor Frid, Marcin Bednarski   +2 more
openaire   +1 more source

ARIES-RS loss of coolant accident (LOCA) analysis

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002
Loss of Coolant Accident (LOCA) analysis has been performed for the ARIES-RS fusion power plant. LOCA occurs when one or more supply tubes outside the reactor are damaged or ruptured preventing the coolant from reaching the in-vessel components. For this analysis, it is assumed that the plasma is immediately quenched and the temperature of the chamber ...
E.A. Mogahed, H. Khater, I.N. Sviatoslavsky, L. El-Guebaly   +3 more
openaire   +1 more source

Loss-of-Coolant Accidents in Small Compact Nuclear Reactors

Nuclear Technology, 1979
The maximum credible accident for which a nuclear reactor nust be analyzed is a loss-of-coolant accident (LOCA) due to a major rupture in the primary system. Such an accident has been analyzed for a conceptual design of a consolidated nuclear steam system (CNSS) using the thermal-hydraulic computer code RELAP4/MOD5.
R. C. Sanders, G. E. Mueller
openaire   +1 more source

Coolant Recirculation in a Pressurized Water Reactor Core under Loss-of-Coolant Accident Conditions

Nuclear Science and Engineering, 1988
A model has been developed to predict the thermal hydraulics in the uncovered part of a pressurized water reactor core.
M. K. Moallemi, R. Viskanta
openaire   +1 more source

The Loss-of-Coolant Accident Analysis in Pressurized Water Reactors

Nuclear Science and Engineering, 1969
A generalized digital computer approach to analyze the loss-of-coolant accident in pressurized water reactors requires a systematic specification of the plant geometric, physical, and topological c...
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Review of Existing Codes for Loss-of-Coolant Accident Analysis

1977
Within the last two years it has become customary in the United States to categorize all LOCA codes into two main groupings: the codes employed in the licensing application which obey the conservative assumptions prescribed by the NRC Acceptance Criteria described in Appendix K to 10 CFR 100 (1).
openaire   +1 more source