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Wyszukujesz frazę "transients" wg kryterium: Temat


Wyświetlanie 1-2 z 2
Tytuł:
Technical solutions for the control and command system of a Plasma Focus device
Autorzy:
Martin, D. I.
Zoita, V. I.
Cotruta, D. A.
Jianu, A. V.
Ighigeanu, D. I.
Bestea, V. I.
Powiązania:
https://bibliotekanauki.pl/articles/147621.pdf
Data publikacji:
2001
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
control system
electromagnetic transients
galvanic separation
plasma focus
Opis:
The paper presents the technical problems related to the electrical control and command system (ECC system) for the plasma focus installation IPF-4/5A having the following main parameters: 1 MA plasma current and 40 kJ energy stored at 20 kV charging voltage. The ECC system applies 23 interlocked logical commands, acquires and processes 28 logical states, acquires, processes and displays continuously the main slow-varying signals coming from IPF-4/5A subassemblies. All the plasma focus installation operational sequences are governed by strict hard and soft interlocking using in parallel two control and command systems: one based on PC-control methods and another based on classical control techniques.
Źródło:
Nukleonika; 2001, 46, suppl. 1; 89-91
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Accidents of loss of flow for the ETTR-2 reactor: deterministic analysis
Autorzy:
El-Messiry, M.
Powiązania:
https://bibliotekanauki.pl/articles/146728.pdf
Data publikacji:
2000
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
design base accidents
LOFA
loss of flow
pump coastdown
reactor transients
Opis:
The main objective for reactor safety is to keep the fuel in a thermally safe condition with adequate safety margins during all operational modes (normal-abnormal and accidental states). To achieve this purpose an accident analysis of different design base accident (DBA) as loss of flow accident (LOFA), is required for assessing reactor safety. The present work concerns this transients applied to Egypt Test and Research Reactor ETRR-2 (new reactor). An accident analysis code FLOWTR is developed to investigate the thermal behaviour of the core during such flow transients. The active core is simulated by two channels: 1 - hot channel (HC), and 2 - average channel (AC) representing the remainder of the core. Each channel is divided into four axial sections. The external loop, core plene, and core chimney are simulated by different dynamic lumps. The code includes modules for pump coast down, flow regimes, decay heat, temperature distributions, and feedback coefficients. FLOWTR is verified against results from RETRAN code, THERMIC code and commissioning tests for null transient case. The comparison shows a good agreement. The study indicates that for LOFA transients, provided the scram system is available, the core is shutdown safely by low flow signal (496.6 kg/s) at 1.4 s where the HC temperature reaches the maximum value of 45.64°C after shutdown. On the other hand, if the scram system is unavailable, and at t=47.33 s, the core flow decreases to 67.41 kg/s, the HC temperature increases to 164.02°C, and the HC clad surface heat flux exceeds its critical value of 400.00 W/cm2 resulting from the fuel burnout.
Źródło:
Nukleonika; 2000, 45, 4; 229-233
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-2 z 2

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