scholarly journals HEAT TRANSFER STUDIES FOR THE D$sub 2$O POWER REACTOR PROGRAM. A Terminal Status Report of the Work at Columbia University.

1966 ◽  
Author(s):  
J.S. Neill
Keyword(s):  
Heat Transfer ◽  
Power Reactor ◽  
Status Report ◽  
Columbia University

NUMERICAL HEAT TRANSFER STATUS REPORT

1995 ◽  
Vol 27 (1) ◽  
pp. iii-iii ◽  
Author(s):  
W. J. Minkowycz ◽  
E. M. Sparrow
Keyword(s):  
Heat Transfer ◽  
Status Report ◽  
Numerical Heat Transfer

FUNDAMENTAL STUDIES IN HEAT TRANSFER AND FLUID MECHANICS. Status Report July 1, 1959-Feb. 29, 1960

1961 ◽  
Author(s):  
H W Hoffman ◽  
W R Gambill ◽  
Keyes, Jr, J J ◽  
Kidd, Jr, G J
Keyword(s):  
Heat Transfer ◽  
Fluid Mechanics ◽  
Status Report

scholarly journals Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation

2021 ◽  
Vol 9 (2B) ◽  
Author(s):  
EDUARDO MADEIRA BORGES ◽  
GAIANÊ SABUNDJIAN
Keyword(s):  
Heat Transfer ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Power Reactor ◽  
Reactor Core ◽  
Flow Regimes ◽  
Nuclear Power Reactor ◽  
Primary Loop ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant

The aim of this paper is evaluated the consequences to ANGRA 2 nuclear power reactor and to identify the flow regimes, the heat transfer modes, and the correlations used by RELAP5/MOD3.2.gama code in ANGRA 2 during the Small-Break Loss-of-Coolant Accident (SBLOCA) with a 200cm2 of rupture area in the cold leg of primary loop. The Chapter 15 of the Final Safety Analysis Report of ANGRA 2 (FSAR-A2) reports this specific kind of accident. The results from this work demonstrated the several flow regimes and heat transfer modes that can be present in the core of ANGRA 2 during the postulated accident. The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2. Additionally, the results showed the correct actuation of the ECCS guaranteeing the integrity of the reactor core.

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