scholarly journals Modeling heat generation and flow in the Advanced Neutron Source Corrosion Test Loop specimen

1988 ◽  
Author(s):  
R. E. Pawel ◽  
D. W. Yarbrough
Keyword(s):  
Neutron Source ◽  
Heat Generation ◽  
Corrosion Test ◽  
Test Loop

Transient Boiling and Cross Flow in 5×5 Rod Bundle With Rapid Heating

2018 ◽  
Author(s):  
Hiroki Takiguchi ◽  
Masahiro Furuya ◽  
Takahiro Arai ◽  
Kenetsu Shirakawa
Keyword(s):  
Fuel Assembly ◽  
Heat Generation ◽  
Cross Flow ◽  
Nuclear Safety ◽  
Wire Mesh ◽  
Coolant Temperature ◽  
Heat Output ◽  
Rod Bundle ◽  
Test Loop ◽  
The Cross

Rapid thermal elevation in nuclear reactor is an important factor for nuclear safety. It is indispensable to develop a three-dimensional nuclear thermal transient analysis code and confirm its validity in order to accurately evaluate the effectiveness of the running nuclear safety measures when heating power of reactor core rapidly rises. However, the heat transfer characteristics such as reactivity feedback characteristics due to moderator density and the technical knowledge explaining the uncertainty are insufficient. In particular, the cross propagation behavior of vapor bubble (void) in cross section of fuel assembly is not grasped. This study evaluates the cross propagation void behavior in a simulated fuel assembly at time of rapid heat generation with a thermal hydraulic test loop including a 5 × 5 rod bundle having the heat generation profile in the flow cross sectional direction. In this paper, the branching heat output condition of transient cross propagation was investigated from visualization of high speed video camera and void fraction measurement by wire mesh sensor with the inlet flow rate 0.3m/s and the inlet coolant temperature 40°C, which are based on the transient safety analysis condition. In addition, we applied the particle imaging velocimetry (PIV) technique to measure liquid-phase velocity profile of the coolant in the transient cross flow and experimentally clarified the relationship with the cross flow.

An Instrumented Field Corrosion Test Loop

1998 ◽  
Author(s):  
Alebachew Demoz ◽  
Kirk H. Michaelian ◽  
John Donini ◽  
Sankara Papavinasam ◽  
R. Winston Revie
Keyword(s):  
Weight Loss ◽  
Corrosion Rate ◽  
Corrosion Test ◽  
Visual Inspection ◽  
Electrochemical Methods ◽  
Corrosion Rates ◽  
Test Loop ◽  
The Media ◽  
Electrochemical Monitoring ◽  
Multi Phase

A multi-purpose instrumented loop in line with an oil producing well is described. The loop has several ports for coupons which were replaced periodically. Some of the coupons were used for electrochemical monitoring in addition to weight loss and visual inspection. Weight loss, pit rate and all the electrochemical methods used gave corrosion rates that were dependent on the positions of the coupons inside the loop. The corrosion rate of the coupons increased from top to bottom. This order reflected the media and flow to which the coupons were exposed in a multi-phase producing well.

scholarly journals Advanced neutron source reactor thermal-hydraulic test loop facility description

1994 ◽  
Author(s):  
D.K. Felde ◽  
G. Farquharson ◽  
J.H. Hardy ◽  
J.F. King ◽  
M.T. McFee ◽  
...  
Keyword(s):  
Neutron Source ◽  
Hydraulic Test ◽  
Test Loop

Corrosion Test Loop

2008 ◽  
pp. 36-36-12 ◽  
Author(s):  
T-L Yau ◽  
RT Webster
Keyword(s):  
Corrosion Test ◽  
Test Loop

scholarly journals URANIUM-BISMUTH IN-PILE CORROSION TEST LOOP. RADIATION LOOP NO. 1

1961 ◽  
Author(s):  
C.H. Waide ◽  
L.E. Kukacka ◽  
R.A. Meyer ◽  
J. Milau ◽  
J.H. Klein ◽  
...  
Keyword(s):  
Corrosion Test ◽  
Radiation Loop ◽  
Test Loop

The corrosion of 6061 aluminum under heat transfer conditions in the ANS corrosion test loop

1991 ◽  
Vol 36 (1-2) ◽  
pp. 175-194 ◽  
Author(s):  
R. E. Pawel ◽  
G. L. Yoder ◽  
D. K. Felde ◽  
B. H. Montgomery ◽  
M. T. McFee
Keyword(s):  
Heat Transfer ◽  
Corrosion Test ◽  
Test Loop

The Design and Fabrication of the Lead Corrosion Test Loop

2006 ◽  
Author(s):  
Chungho Cho ◽  
Woonkyu Lee ◽  
Choonho Cho ◽  
Jongman Kim ◽  
Tae Yung Song
Keyword(s):  
Corrosion Test ◽  
Isothermal Condition ◽  
Liquid Lead ◽  
Fuel Cladding ◽  
Initial Operation ◽  
Energy Research ◽  
General Design ◽  
Lead Corrosion ◽  
Test Loop

Lead corrosion test loop named KPAL-II (KAERI Pb Alloy Loop II) has been designed and fabricated at the Korea Atomic Energy Research Institute (KAERI) and an initial operation was performed recently. The KPAL-II was designed to study the long-term corrosive effects of liquid lead on structural and fuel cladding materials at temperatures up to 600°C. The first run of KPAL-II took place on March 15th, 2006 and three hundred hours of shakedown testing were performed with an isothermal condition at about 450°C. This paper summarizes the general design concept and the results of the shakedown testing of KPAL-II.

Heat Generation and Transport in the Earth

2010 ◽  
Author(s):  
Claude Jaupart ◽  
Jean-Claude Mareschal
Keyword(s):  
Heat Generation ◽  
The Earth

Design of a Neutron Source for Calibration

2002 ◽  
Author(s):  
Aureliano Carrillo-Nuñez
Keyword(s):  
Neutron Source
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