Decay heat removal and natural convection in fast breeder reactors

1982 ◽  
Vol 3 (4) ◽  
pp. 230
Author(s):  
B.N. Furber ◽  
G. Hulme
Keyword(s):  
Natural Convection ◽  
Heat Removal ◽  
Decay Heat ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

Thermohydraulic Investigations of Decay Heat Removal Systems by Natural Convection for Liquid-Metal Fast Breeder Reactors

1989 ◽  
Vol 88 (1) ◽  
pp. 75-86 ◽  
Author(s):  
Helmut Hoffmann ◽  
Dietrich Weinberg ◽  
Yoshiaki Ieda ◽  
Klaus Marten ◽  
Herbert Tschöke ◽  
...  
Keyword(s):  
Natural Convection ◽  
Liquid Metal ◽  
Heat Removal ◽  
Decay Heat ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

Porous Body Model Based Parametric Study for Sodium to Air Heat Exchanger Used in Fast Reactors

2015 ◽  
Vol 8 (1) ◽  
Author(s):  
S. P. Pathak ◽  
V. A. Suresh Kumar ◽  
I. B. Noushad ◽  
K. K. Rajan ◽  
K. Velusamy ◽  
...  
Keyword(s):  
Porous Body ◽  
Removal Rate ◽  
Heat Removal ◽  
Test Facility ◽  
Outlet Temperature ◽  
Finned Tubes ◽  
Decay Heat ◽  
Body Model ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

Sodium to air heat exchangers (AHX) with finned tubes is used in fast breeder reactors for decay heat removal. The aim of decay heat removal is to maintain the fuel, clad, coolant, and structural temperatures within safety limits. To investigate the thermal hydraulic features of AHX, a robust porous body based computational fluid dynamics (CFD) model has been developed and validated against the experimental data obtained from a model AHX of 2 MW capacity in Steam Generator Test Facility at the Indira Gandhi Centre for Atomic Research, Kalpakkam. In the present paper, the developed porous body model is used to study the sodium and air temperature distribution and the influence of various parameters that affect the heat removal rate and sodium outlet temperature in full-size AHX used in the fast breeder reactors. The parameters include mass flow rates and inlet temperatures of sodium and air. The focus of the study has been to identify conditions that can pose the risk of sodium freezing.

Validation Experiment for the Cooling Capability of Passive Auxiliary Feedwater System (PAFS) With PASCAL Facility

2012 ◽  
Author(s):  
Byoung-Uhn Bae ◽  
Seok Kim ◽  
Yu-Sun Park ◽  
Bok-Deuk Kim ◽  
Kyoung-Ho Kang ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Natural Convection ◽  
Heat Exchanger ◽  
System Analysis ◽  
Thermal Power ◽  
Heat Removal ◽  
Steady State Condition ◽  
Single Tube ◽  
Decay Heat ◽  
Validation Experiment

The Passive Auxiliary Feedwater System (PAFS) is one of the advanced safety features adopted in the APR+ (Advanced Power Reactor Plus) which is intended to completely replace the conventional active auxiliary feedwater system. It removes the decay heat by cooling down the secondary system of the SG using condensation heat exchanger installed in the Passive Condensation Cooling Tank (PCCT). With an aim of validating the cooling and operational performance of the PAFS, PASCAL (PAFS Condensing Heat Removal Assessment Loop), was constructed to experimentally investigate the condensation heat transfer and natural convection phenomena in the PAFS. It simulates a single tube of the passive condensation heat exchangers, a steam-supply line, a return-water line, and a PCCT with a reduced area, which is equivalent to 1/240 of the prototype according to a volumetric scaling methodology with a full height. The objective of the experiment is to investigate the cooling performance and natural circulation characteristics of the PAFS by simulating a steady state condition of the thermal power. From the experiment, two-phase flow phenomena in the horizontal heat exchanger and PCCT were investigated and the cooling capability of the condensation heat exchanger was validated. Test results showed that the design of the condensation heat exchanger in PAFS could satisfy the requirement for heat removal rate of 540 kW per a single tube and the prevention of water hammer phenomenon inside the tube. It also proved that the operation of PAFS played an important role in cooling down the decay heat by natural convection without any active system. The present experimental results will contribute to improve the model of the condensation and boiling heat transfer, and also to provide the benchmark data for validating the calculation performance of a thermal hydraulic system analysis code with respect to the PAFS.

Flow Excursion-Induced Dryout at Low Heat Flux Natural Convection Boiling

1986 ◽  
Vol 108 (2) ◽  
pp. 425-432 ◽  
Author(s):  
M. Khatib-Rahbar ◽  
E. G. Cazzoli
Keyword(s):  
Experimental Data ◽  
Heat Flux ◽  
Natural Convection ◽  
High Heat ◽  
High Heat Flux ◽  
Two Dimensional ◽  
Boiling Process ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Saturated Boiling

Flow excursion-induced dryout at low heat flux natural convection boiling, typical of liquid metal fast breeder reactors, is addressed. Steady-state calculations indicate that low-quality boiling is possible up to the point of the Ledinegg instability, leading to flow excursion and subsequent dryout in agreement with experimental data. A flow regime-dependent critical heat flux relationship based upon a saturated boiling criterion is also presented. Transient analyses indicate that premature flow excursion cannot be ruled out and the boiling process is transient dependent. Analysis of a loss-of-flow transient at high heat flux forced convection shows a significantly faster flow excursion leading to dryout, which is in excellent agreement with the results of the two-dimensional THORAX code.

Post shut-down decay heat removal from nuclear reactor core by natural convection loops in sodium pool

2016 ◽  
Vol 301 ◽  
pp. 59-73 ◽  
Author(s):  
A. Rajamani ◽  
T. Sundararajan ◽  
B.V.S.S.S. Prasad ◽  
U. Parthasarathy ◽  
K. Velusamy
Keyword(s):  
Natural Convection ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Heat Removal ◽  
Decay Heat ◽  
Nuclear Reactor Core
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