Melcor Modeling Of The Pbf Severe Fuel Damage Test 1 4
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MELCOR Modeling of the PBF (Power Burst Facility) Severe Fuel Damage Test 1-4
Author | : |
Publisher | : |
Total Pages | : 6 |
Release | : 1990 |
Genre | : |
ISBN | : |
This paper describes a MELCOR Version 1.8 simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) Test 1--4. The input data for the analysis were obtained from the Test Results Report and from SCDAP/RELAP5 input. Results are presented for the transient liquid level in the test bundle, clad temperatures, shroud temperatures, clad oxidation and hydrogen generation, bundle geometry changes, fission product release, and heat transfer to the bypass flow. Comparisons are made with experimental data and with SCDAP/RELAP5 calculations. 10 refs., 7 figs.
MELCOR Simulation of the PBF (Power Burst Facility) Severe Fuel Damage Test 1-1
Author | : |
Publisher | : |
Total Pages | : |
Release | : 1989 |
Genre | : |
ISBN | : |
This paper describes a MELCOR version 1.7.1 simulation of the Power Burst Facility (PBF) Severe Fuel Damage (SFD) 1-1 test. The input data for the simulation was obtained from the SFD 1-1 Test Results Report and from SCDAP input. Results are presented for the transient two-phase interface level in the core, fuel and clad temperatures at various elevations in the fuel bundle, clad oxidation, hydrogen generation, fission product release, and heat transfer to the surrounding structures. Comparisons are made with experimental data and predictions from STCP and the NRC's mechanistic code SCDAP (version 18). 6 refs., 12 figs.
PBF Severe Fuel Damage Test 1-1
Author | : Zoel R. Martinson |
Publisher | : |
Total Pages | : |
Release | : 1986 |
Genre | : Light water reactors |
ISBN | : |
PBF Severe Fuel Damage Test 1-1: Appendices A through I
Author | : Zoel R. Martinson |
Publisher | : |
Total Pages | : |
Release | : 1986 |
Genre | : Light water reactors |
ISBN | : |
Nuclear Thermal Hydraulic and Two-Phase Flow
Author | : Jun Wang |
Publisher | : Frontiers Media SA |
Total Pages | : 120 |
Release | : 2018-10-11 |
Genre | : |
ISBN | : 2889456129 |
Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.