Performance Evaluation of Control and Safety Rod and Its Drive Mechanism of Fast Breeder Reactor During Seismic Event

2006 ◽  
Author(s):  
P. Chellapandi ◽  
V. Rajan Babu ◽  
S. C. Chetal ◽  
Raj Baldev
Keyword(s):  
Seismic Event ◽  
Structural Integrity ◽  
Reactor Core ◽  
Seismic Loading ◽  
Operating Conditions ◽  
Seismic Events ◽  
Fast Breeder Reactor ◽  
Mechanical Interaction ◽  
Life Situation ◽  
Drop Time

Control and safety rods & their drive mechanisms (CSRDM) and diverse safety rods & their drive mechanisms (DSRDM) are the main constituents of the two independent shutdown systems in Prototype Fast Breeder Reactor (PFBR) of 500 MWe. There are nine CSR and three DSR placed within the hexagonal sheaths, which in turn are located in two radial banks of reactor core. This paper deals with the analysis carried out to predict the performance of CSRDM along with CSR. Analysis is carried out for the static and seismic loading under the fuel handling as well as normal operating conditions with the objective of ensuring structural integrity as well as to estimate the drop time during seismic event. The effects of bowing of sub-assemblies corresponding to the end of life situation have been considered. From the analysis, it is found that the drop time of CSR is 0.82 s, which is less than 1 s, and hence there is no concern of reactor shutdown. Further, it is ensured that there is no mechanical interaction of concern between various parts. The induced stresses are found to be very much less than RCC-MR allowable stress intensity. Thus the performance of CSRDM and CSR is demonstrated to be sound during normal as well as seismic events.

Application of Acoustic Technique for Surveillance and Anomaly Detection in LMFBRs

2008 ◽  
Author(s):  
V. Prakash ◽  
M. Anandaraj ◽  
M. Thirumalai ◽  
P. Kalyanasundaram ◽  
G. Vaidyanathan
Keyword(s):  
Detection System ◽  
High Reliability ◽  
Reactor Core ◽  
Performance Testing ◽  
Free Fall ◽  
Operating Conditions ◽  
Fast Breeder Reactor ◽  
Steam Generators ◽  
Acoustic Technique ◽  
Drop Time

Acoustic techniques find wide application in Liquid Metal Fast Breeder Reactors (LMFBRs) for ensuring its high reliability, safety and plant availability. Various surveillance methods based on acoustic technique can be employed in these reactors to detect deviations from normal operating conditions. This could be used for the measurement of drop time of Diverse Safety Rods (DSRs) in the core, detection of in-sodium water leaks in Steam Generators, cavitation detection in sodium pumps and reactor core components. An active R&D program is being pursued in these areas at Indira Gandhi Centre for Atomic Research. Acoustic measurement technique has been used to determine the drop time of Diverse Safety Rods in sodium. 3 nos of Diverse Safety Rods (DSRs) are provided in Prototype Fast Breeder Reactor (PFBR) for its safe shut down in case of a SCRAM. An online drop time measurement system using acoustic technique is planned to detect the proper insertion of DSRs into their corresponding Subassemblies. Experiments were conducted during the performance testing of DSRs in sodium using accelerometer instrumented wave-guide system and free fall time and braking time of DSR have been measured. For detection of in-sodium water leaks in Steam Generators, acoustic method serves as a supplementary monitoring technique with an intermediate sensitivity and instantaneous response. To develop an acoustic leak detection system for Steam Generators of Prototype Fast Breeder Reactor, preliminary studies on the behavior of micro leak and its propagation has been carried out in Sodium Water Reaction Test Rig, injecting steam into sodium. Acoustic technique was employed to characterize the onset of leak. Cavitation in LMFBRs can occur in fuel subassemblies, pressure drop devices, pumps etc. It is important to minimize cavitation to reduce the risk of damage from erosion. Acoustic technique was extensively used in qualifying Prototype Fast Breeder Reactor components against cavitation phenomenon. This paper discusses the various experiments carried out towards the development of the acoustic surveillance methods for FBRs, instrumentation involved, results obtained from experiments and brief details of the future programme.

scholarly journals Mode I Crack Propagation Experimental Analysis of Adhesive Bonded Joints Comprising Glass Fibre Composite Material under Impact and Constant Amplitude Fatigue Loading

Materials ◽  
2021 ◽  
Vol 14 (16) ◽  
pp. 4380
Author(s):  
Alirio Andres Bautista Villamil ◽  
Juan Pablo Casas Rodriguez ◽  
Alicia Porras Holguin ◽  
Maribel Silva Barrera
Keyword(s):  
Crack Propagation ◽  
Structural Integrity ◽  
Crack Propagation Rate ◽  
Fatigue Loading ◽  
Propagation Rate ◽  
Operating Conditions ◽  
Impact Testing ◽  
Mode I ◽  
Mode I Crack ◽  
Constant Amplitude

The T-90 Calima is a low-wing monoplane aircraft. Its structure is mainly composed of different components of composite materials, which are mainly bonded by using adhesive joints of different thicknesses. The T-90 Calima is a trainer aircraft; thus, adverse operating conditions such as hard landings, which cause impact loads, may affect the structural integrity of aircrafts. As a result, in this study, the mode I crack propagation rate of a typical adhesive joint of the aircraft is estimated under impact and constant amplitude fatigue loading. To this end, effects of adhesive thickness on the mechanical performance of the joint under quasistatic loading conditions, impact and constant amplitude fatigue in double cantilever beam (DCB) specimens are experimentally investigated. Cyclic impact is induced using a drop-weight impact testing machine to obtain the crack propagation rate (da/dN) as a function of the maximum strain energy release rate (GImax) diagram; likewise, this diagram is also obtained under constant amplitude fatigue, and both diagrams are compared to determine the effect of each type of loading on the structural integrity of the joint. Results reveal that the crack propagation rate under impact fatigue is three orders of magnitude greater than that under constant amplitude fatigue.

Numerical and Experimental Investigations on Liner Heat Transfer in an Aero Engine Combustion Chamber

2017 ◽  
Author(s):  
Korukonda Venkata Lakshmi Narayana Rao ◽  
B. V. S. S. S. Prasad ◽  
Ch. Kanna Babu ◽  
Girish K. Degaonkar
Keyword(s):  
Combustion Chamber ◽  
Structural Integrity ◽  
Operating Conditions ◽  
Experimental Investigations ◽  
Numerical Computations ◽  
Combustion Gases ◽  
Flow Characterization ◽  
Aero Engine ◽  
Straight Flow ◽  
Flow Variables

The Gas turbine combustion chamber is the highest thermally loaded component where the temperature of the combustion gases is higher than the melting point of the liner that confines the gases. Combustor liner temperatures have to be evaluated at all the operating conditions in the operating envelope to ensure a satisfactory liner life and structural integrity. On experimental side the combustion chamber rig testing involves a lot of time and is very expensive, while the numerical computations and simulations has to be validated with the experimental results. This paper is mainly based on the work carried out in validating the liner temperatures of a straight flow annular combustion chamber for an aero engine application. Limited experiments have been carried out by measuring the liner wall temperatures using k-type thermocouples along the liner axial length. The experiments on the combustion chamber testing are carried out at the engine level testing. The liner temperature which is numerically computed by CHT investigations using CFX code is verified with the experimental data. This helped in better understanding the flow characterization around and along the liner wall. The main flow variables used are the mass flow rate, temperature and the pressure at the combustor inlet. Initially, the fuel air ratio is used accordingly to maintain the same T4/T3 ratio. The effect of liner temperature with T3 is studied. Since T4 is constant, the liner temperature is only dependent on T3 and follows a specific temperature distribution for the given combustor geometry. Hence this approach will be very useful in estimating the liner temperatures at any given T3 for a given combustor geometry. Further the liner temperature is also estimated at other fuel air ratios (different T4/T3 ratios) by using the verified CHT numerical computations and found that TL/T3 remains almost constant for any air fuel ratio that is encountered in the operating envelope of the aero engine.

The Koyna earthquake of December 10 1967: A multiple seismic event

1971 ◽  
Vol 61 (1) ◽  
pp. 167-176 ◽  
Author(s):  
Harsh K. Gupta ◽  
B. K. Rastogi ◽  
Hari Narain
Keyword(s):  
Seismic Event ◽  
Strong Motion ◽  
Seismic Events ◽  
Field Observations ◽  
Rupture Velocity ◽  
P Waves ◽  
Seismic Arrays ◽  
Sine Curve ◽  
Curve Method ◽  
Different Origin

abstract The analysis of P waves recorded at seismological observatories and seismic arrays at teleseismic distances and strong motion seismographs located at Koyna Dam suggest the Koyna earthquake of December 10 1967 to be a complex multiple event. Six of the events could be identified, and the second and third events are located with respect to the initiation using the Gutenberg sine-curve method at distances of 6 and 17 km due south, the average rupture velocity being 3.4 km/sec. The findings are consistent with the field observations and the different origin times, epicenters and magnitudes reported for the earthquake. Seismic array records are found to be very useful in examining the multiplicity of seismic events.

Sodium-Free Level Fluctuations: Concern on Structural Integrity for the Pool-Type Sodium-Cooled Fast Breeder Reactor

2017 ◽  
pp. 407-417
Author(s):  
V. R. Chandan Reddy ◽  
R. Suresh Kumar ◽  
Anil Kumar Sharma ◽  
K. Velusamy ◽  
P. Selvaraj
Keyword(s):  
Structural Integrity ◽  
Fast Breeder Reactor ◽  
Free Level ◽  
Pool Type

Assessment of RELAP/SCDAPSIM for Turbine Trip Transient in NuScale-SMR

2018 ◽  
Author(s):  
Katarzyna Skolik ◽  
Anuj Trivedi ◽  
Marina Perez-Ferragut ◽  
Chris Allison
Keyword(s):  
Natural Circulation ◽  
System Modeling ◽  
Thermal Power ◽  
Reactor Core ◽  
Operating Conditions ◽  
Severe Accident ◽  
Circulation System ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Secondary Steam

The NuScale Small Modular Reactor (SMR) is an integrated Pressurized Water Reactor (iPWR) with the coolant flow based on the natural circulation. The reactor core consists of 37 fuel assemblies similar to those used in typical PWRs, but only half of their length to generate 160MW thermal power (50 MWe). Current study involves the development of a NuScale-SMR model based on its Design Certification Application (DCA) data (from NRC) using RELAP/SCDAPSIM. The turbine trip transient (TTT) was simulated and analysed. The objective was to assess this version of the code for natural circulation system modeling capabilities and also to verify the input model against the publicly available TTT results obtained using NRELAP5. This successful benchmark confirms the reliability of the thermal hydraulic model and allows authors to use it for further safety and severe accident analyses. The reactor core channels, pressurizer, riser and downcomer pipes as well as the secondary steam generator tubes and the containment were modeled with RELAP5 components. SCDAP core and control components were used for the fuel elements in the core. The final input deck achieved the steady state with the operating conditions comparable to those reported in the DCA. RELAP/SCDAPSIM predictions are found to be satisfactory and comparable to the reference study. It confirms the code code capabilities for natural circulation system transients.

SIMULASI KARAKTERISTIK ALIRAN DAN SUHU FLUIDA PENDINGIN (H2O) PADA TERAS REAKTOR NUKLIR SMR (SMALL MODULAR REACTOR)

ROTASI ◽  
2013 ◽  
Vol 15 (4) ◽  
pp. 33
Author(s):  
Anwar Ilmar Ramadhan ◽  
Indra Setiawan ◽  
M. Ivan Satryo
Keyword(s):  
Fluid Flow ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Heat Removal ◽  
Axial Direction ◽  
Operating Conditions ◽  
Fluid Temperature ◽  
Wide Range ◽  
Fuel Reactor ◽  
Performance Of Heat Transfer

Safety is an issue that is of considerable concern in the design, operation and development of a nuclear reactor. Therefore, the method of analysis used in all these activities should be thorough and reliable so as to predict a wide range of operating conditions of the reactor, both under normal operating conditions and in the event of an accident. Performance of heat transfer to the cooling of nuclear fuel, reactor safety is key. Poor heat removal performance would threaten the integrity of the fuel cladding which could further impact on the release of radioactive substances into the environment in an uncontrolled manner to endanger the safety of the reactor workers, the general public, and the environment. This study has the objective is to know is profile contour of fluid flow and the temperature distribution pattern of the cooling fluid is water (H2O) in convection in to SMR reactor with fuel sub reed arrangement of hexagonal in forced convection. In this study will be conducted simulations on the SMR reactor core used sub channel hexagonal using CFD (Computational Fluid Dynamics) code. And the results of this simulation look more upward (vector of fluid flow) fluid temperature will be warm because the heat moves from the wall to the fluid heater. Axial direction and also looks more fluid away from the heating element temperature will be lower.

Early Cambrian Seismic Events and Their Tectonic Significance in Western Zhejiang

2012 ◽  
Vol 524-527 ◽  
pp. 42-48
Author(s):  
Fu Sheng Guo ◽  
Zhao Bin Yan ◽  
Liu Qin Chen
Keyword(s):  
Seismic Event ◽  
Regional Distribution ◽  
Sedimentary Rocks ◽  
Seismic Events ◽  
Time Interval ◽  
Early Cambrian ◽  
Distribution Characteristics ◽  
Early Paleozoic ◽  
Tectonic Events ◽  
Tectonic Significance

The two early Cambrian seismic events could be found from sedimentary rocks at Peilingjiao section of Kaihua County, Baishi and Fangcun sections of Changshan County in western Zhejiang, except for Jiangshan area. The seismic event at Baishi outcrop can be correlated to the second seismic event at Peilingjiao section. Taking Fangcun as epicenter of the second seismic event, the magnitude of paleoseism in western Zhejiang is about 7~7.6. According to investigation on regional distribution of seismic events, the two seismic activities should be regulated by large Kaihua-Chun’an fault, but unrelated with Jiangshan-Shaoxing fault or Changshan-Xiaoshan fault. However, the formation time of Kaihua-Chun’an fault has not yet been determinate. Based on controlling on Silurian, the possible formation age was inferred to early Paleozoic. The distribution characteristics of seismites indicate that the Kaihua-Chun’an fault was already being active during early Cambrian and seismic activities may be response to Sinian tectonic events in western Zhejiang. By the way of analysis on paleoseismic rhythm, the time interval of the two seismic events in western Zhejiang is less than 5.0 Ma, which may be the result of early frequent activities of Kaihua-Chun’an fault.

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