Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor

2013 ◽  
Vol 55 ◽  
pp. 302-311 ◽  
Author(s):  
B.X. Hu ◽  
Y.W. Wu ◽  
W.X. Tian ◽  
G.H. Su ◽  
S.Z. Qiu
Keyword(s):  
Fast Reactor ◽  
Transient Thermal

The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on Both Surfaces

1982 ◽  
Vol 104 (3) ◽  
pp. 239-244
Author(s):  
J. Phillips
Keyword(s):  
Thermal Cycling ◽  
Strain Hardening ◽  
Fast Reactor ◽  
Material Properties ◽  
Thermal Loading ◽  
Mechanical Load ◽  
Accumulation Of Damage ◽  
Transient Thermal

Previously reported computations are extended to analyze a Bree plate subjected to steady mechanical load and cyclic thermal downshocks on both surfaces. It is shown that two critical plate thicknesses can be identified, one below which thermal cycling has no effect, and one above which the full effects of rapid transient thermal loading are observed. The significant effects which material properties, such as the degree of strain hardening present, can have on the plate behavior are also illustrated. These findings are relevant to design of fast reactor components which experience loadings of this type.

Validation of THACS for Sodium Cooled Fast Reactor Based on Benchmark Analysis of EBR-II

2014 ◽  
Author(s):  
Yue Nina ◽  
Ma Zaiyong ◽  
Hu Benxue ◽  
Suizheng Qiu ◽  
Guanghui Su
Keyword(s):  
Fast Reactor ◽  
Channel Model ◽  
Flow Characteristics ◽  
Primary Loop ◽  
Reactor Kinetics ◽  
Multiple Channel ◽  
Benchmark Analysis ◽  
The Core ◽  
Intermediate Heat Exchanger ◽  
Transient Thermal

In this paper the thermal-hydraulic characteristics of the primary loop of the Experimental Breeder Reactor (EBR-II), including the temperature and the flow characteristics of the core, the intermediate heat exchanger (IHX) and the experiment subassembly XX09 and XX10, were analyzed with the transient thermal-hydraulic code THACS. The THACS code contains the core, the pumps, IHX, the sodium pool and some other modules, and each module could operate separately. All of the primary–loop components are simulated one-dimensional, and in the core calculation the incompressible model for the single phase. The multiple-channel model is applied to simulate the core subassemblies, including the average, hot, XX09, XX10, the reflector and the blanket channels. The neutron physics is calculated with the point reactor kinetics, and the reactivity feedbacks caused by the Doppler effect, coolant density, axial expansion of fuel rods and radial expansion of core are considered. Two tests, namely the SHRT-17 and SHRT-45R tests, are simulated to validate our tools and models. The THACS simulation results show that the EBR-II type sodium cooled fast reactor could shut down automatically relying on inherent negative feedbacks in the two tests.

The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on One Surface

1982 ◽  
Vol 104 (3) ◽  
pp. 232-238 ◽  
Author(s):  
J. Phillips
Keyword(s):  
Fatigue Damage ◽  
Fast Reactor ◽  
Damage Accumulation ◽  
Mechanical Load ◽  
Computer Calculations ◽  
Accumulation Of Damage ◽  
Transient Thermal ◽  
Biot Numbers ◽  
Damage Summation ◽  
Dwell Period

Computer calculations, incorporating analysis of elastic, plastic and creep effects, are performed on a Bree plate subjected to steady mechanical load and cyclic thermal downshocks on one surface. Particular attention is given to the accumulation of creep and fatigue damage which is calculated from the stress-strain distributions using linear damage summation rules. The computations examine the dependence of the damage accumulation on such factors as the applied loads, the degree of hardening in the material, the length of the creep dwell period and the severity of the transient thermal loadings as measured by the Fourier and Biot numbers. This indicates which considerations are likely to be important in the design of fast reactor components which experience loadings of this type.

Research and development of a transient thermal–hydraulic code for system safety analysis of sodium cooled fast reactor

2021 ◽  
Vol 152 ◽  
pp. 107841
Author(s):  
Yang Yu ◽  
Dong Liu ◽  
Xiaoming Song ◽  
Zhongchun Li ◽  
Fengchen Guo ◽  
...  
Keyword(s):  
Research And Development ◽  
Fast Reactor ◽  
Safety Analysis ◽  
System Safety ◽  
Transient Thermal

Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes

2018 ◽  
Vol 337 ◽  
pp. 228-235 ◽  
Author(s):  
Shiying Wei ◽  
Chenglong Wang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
G.H. Su
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Transient Thermal

Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor

2021 ◽  
Author(s):  
Shiying Wei ◽  
Weimin Ma ◽  
Chenglong Wang ◽  
Ronghua Chen ◽  
Wenxi Tian ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Evaluation Code ◽  
Transient Thermal ◽  
Development And Validation

Comparison of Ion-Milling Techniques For Cross-Sectional TEM of Semiconductors

1985 ◽  
Vol 43 ◽  
pp. 166-167
Author(s):  
Julia T. Luck ◽  
C. W. Boggs ◽  
S. J. Pennycook
Keyword(s):  
Analytical Techniques ◽  
Sample Surface ◽  
Ion Milling ◽  
Cross Sectional ◽  
Reliable Technique ◽  
Near Surface ◽  
Transmission Electron ◽  
Thin Region ◽  
Transient Thermal

The use of cross-sectional Transmission Electron Microscopy (TEM) has become invaluable for the characterization of the near-surface regions of semiconductors following ion-implantation and/or transient thermal processing. A fast and reliable technique is required which produces a large thin region while preserving the original sample surface. New analytical techniques, particularly the direct imaging of dopant distributions, also require good thickness uniformity. Two methods of ion milling are commonly used, and are compared below. The older method involves milling with a single gun from each side in turn, whereas a newer method uses two guns to mill from both sides simultaneously.

Current Status of the Development of the Fast Reactor Fuel Cycle in India

2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Current Status ◽  
Fast Reactor Fuel

Current Status of Fast Reactor Critical Experiments

1971 ◽  
Vol 13 (10) ◽  
pp. 582-597
Author(s):  
Shoji NOMOTO ◽  
Tsutomu IIJIMA
Keyword(s):  
Fast Reactor ◽  
Current Status
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