Chapter 7. Design of Steam Generator

Size: px
Start display at page:

Download "Chapter 7. Design of Steam Generator"

Transcription

1 Nuclear Systems Design Chapter 7. Design of Steam Generator Prof. Hee Cheon NO

2 7.1 Overview and Current Issues of S/G Essential Roles of S/G 2

3 3

4 7.1.2 S/G and Its Interfacing Interfacing system of S/G 4

5 Internal system of S/G and Design Values 5

6 6

7 7.1.3 Three Types of S/G Type 1 : Once-through S/G Primary Flow is Downward Secondary Up 7

8 Type 2 : Vertical U-Tube S/G Primary Flow is Up & Down Secondary Up 8

9 Type 3 : Horizontal S/G Primary Flow is Horizontal Secondary Up 9

10 7.1.4 Thermal Behavior in the Secondary Side of S/G Slightly subcooled swirl flow in the downcomer due to saturated rotational flow by primary separators Strong unsymmetrical void distribution between the cold and hot sides Churn-turbulent flow regime is dominant 10

11 7.1.5 Main Current Issues of S/G Tube degradation : Degradation of thermal efficiency, more overall inspection, More radiation exposure of maintenance personnel, high possibility of SG tube break accident SG water level control : Frequent Reactor trip by failure of S/G water level control 11

12 Condensation-induced waterhammer in S/G : Serious structural effect on feedwater lines Design of SG separators : Excessive moisture Excessive costly maintenance Importance of SG role on SB-LOCA : Heat sink by reflux condensation 12

13 7.1.6 S/G Reliability Main Problems of S/G Tube material corrosion 13

14 Tube material corrosion : Wastage or thinning : cyclic boiling and deposition in alternative wetting and drying zone of sludge Primary water initiated cracking Secondary water initiated cracking Pitting 14

15 Tube support & tubesheet corrosion 15

16 16

17 Tube support and tubesheet corrosion : Denting : Cyclic boiling and deposition in crevices by wetting, dryout, and rewetting 17

18 Mechanical damage Mechanical damage : Tube fretting Fatigue cracking 18

19 7.2 Design Improvement of S/G Design Parameters Affecting Reliability of S/G Water chemistry choice : Solid treatment (Phosphate treatment) AVT (All-Volatile Treatment) Material design choices : Tubes : Inconel 600 Inconel 800 More SCC Resistant but lower thermal conductivity 19

20 Tube SupportPlates : Carbon Steel Stainless Steel More Denting Resistant Secondary Plant: Less Cu + Carbon Steel Decelerating Denting Stainless Steel Condenser Tubes: Aluminium Titanium More Chrolide Resistant 20

21 Design choices: Stagnant Regions (near Tube Sheets, Tube SupportPlates) : More Chemistry Concentration 21

22 7.2.2 Design Modification of S/G Objectives of design change Larger circulation ratio : Decreasing potential for local chemical concentration More corrosion resistant materials Increasing secondary-side access for inspection and maintenance 22

23 Practical example : Model F S/G Design Changes WESTINGHOUSE MODEL F STEAM GENERATOR DESIGN CHANGES SUMMARY CHANGES Quatrefoil tube support Ferritic stainless steel tube supports Thermally treated Inconel 600 tubing Access openings Wet layup recirculation connection Separator upgrading PURPOSES Increase circulation Increase margin against corrosion Increase margin against Corrosion Enhance maintainability Enhance maintainability Enhance separation 23

24 24

25 25

26 26

27 27

28 28

29 Feedring Design: Steam-Driven Waterhammer in S/G 29

30 30

31 31

32 Possible sequence events leading to condensation-induced water hammer. [1] 32

33 [2] 33

34 [3] 34

35 [4] 35

36 Solutions : Change pipe layout : Short horizontal pipe length Less acceleration Generation of smaller pressure wave Installation of J nozzles : Problem : some drainage by a built-in leakage at the thermal sleeve (designed for accommodation of thermal expansion) Auxiliary feedwater flow control : Limitation of highly subcooled auxiliary feedwater flow to limit the amount of steam condensed 36

37 Separator: gravitational/primary/secondary(dryer) separators Gravitational Separator: Empty space between primary and secondary separators Very effective to eliminate large droplets 37

38 Primary Separator : Separation through centrifugal force Two competitive requirements : Good separation : vane design to produce large centrifugal force Low pressure drop : vane design to produce small centrifugal force 38

39 Moisture separator Combustion Engineering Type Seperstor 39

40 Three-Dimensional Visualization of Westingouse Steam separator Geomety 40

41 Secondary Separator (Dryer): Chevron type dryer Very effective to eliminate small droplets 41

42 7.3 Design Analysis S/G Prediction of Circulation Ratio Circulation Ratio : CR g h a h g a h K A h Q h h 1/ 2 {[ f ( D f 2 ) g ( g 2 )]/ [ /(2 )]} ( B fg / SG)(1 F / fg ) Parametric effects on CR : Note: A decrease in form loss of tube support plates drives to increase CR. 42

43 Prediction of Circulation Ratio CR m / m m / m m / ( m ) 1/ D F D s D e D e recirculation ratio m / m CR 1 mass m m m D F R energy : Q m ( h h ) m ( h h ) R D 0 i F s F F CR m / m ( h h ) / ( h h ) ( m / Q )( h h ) ( m / Q ) h (1 h / h ) D F s F 0 i D SG g F D SG fg F fg where h h h F f F Measurable quantities : Q, h ( p ), h SG fg s F Unmeasurable quantitiy : m D 43

44 Estimation of : momentum : p p where p [ K / (2 A )] m 2 2 f B D 2 p gh g ( ) dh gh g( ) h d f D g g f f f D g g f f 0 gh g( ) h g( h h ) g( h ) f D g g f f 2 f D f 2 g f 2 Then, we have m D driving force fricton form loss 1/2 m {[ g( h h ) g( h )] / [ K / (2 )]} A D f D f 2 Circulation ratio becomes h g f 2 B CR g h h g h K A h Q h h 1/2 {[ f ( D f 2 ) g( f 2 )] / [ / (2 )]} ( B fg / SG)(1 F / fg) 2 44

45 7.3.2 Determination of Steam Pressure in the S/G Equation for steam pressure: ( UA) T / ( h h ) [( p p )2 / K ] A 1/2 SG ln s F s back s s s where, Tln ( THL TCL ) / ln[( THL Ts ) /( TCL Ts )] Rate of bubble generation in the steam generator (W b ) = steam flow rate in the steam lines (W s ) 45

46 The steam pressure will be increased until the steam flow rate from the steam generator is the same the bubble generation rate: Rate of bubble generation in the steam generator (W b ) W Q / ( h h ) ( UA) T / ( h h ) b SG s F SG ln s F steam flow rate in the steam lines (W s ) ( p p ) K u / 2 K W / ( A ) W [( p p ) / K ] A /2 s back s s s s s s s s s back s s s 46

47 design requirement : maximum pot press=1.5bar design pipe diameter: Q h P P K D 4 4Q 1/2 K 1/4 Dp ( ) [ ] h 2 ( P P ) 1/2 2 / fg [2( pot a ) / ] ( P) fg pot a 47

48 Deter mination of SG pressure Input A, Q, T, T ; Output p, m, W w Rx pin pout SG s tu Q m ( h h ) UA T ; W m ( h h ) SG s s F w LN tu s s Cinlet Q Q UA T T Rx SG w LN SG Q m ( h h ) m SG s s F s W m ( h h ) W tu s turbine, inlet turbine, outlet tu Note : h ~ h s ; h ~ h turbine, inlet turbine, outlet condenser, inlet where T ( T T ) / ln( T / T ) ln [( T T ) ( T T )] / ln[( T T ) / ( T T )] pin SG pout SG pin SG pout SG Comparison : T ( T T ) pavg SG 48

49 Estimation of Reactor Thermal Power by Secondary Calorimetric Method Methods of Rx power measurement in real time to check whether Rx power is operated at or below the licensed Rx power: Measurement of incore neutron det ector : not real time Q Rx K thermal flux Measurement of primary flow rate( W ) : l arg e pressure drop primary Q Q Q Q W c ( T T ); Rx RCP loss SG primary p, primary hot cold Secondary carolim etric method : feedwater flow measurement( W ); accurate and real time method Q Q Q Q Q Q Q Q Rx RCP loss SG Rx SG RCP loss Q W h W h Q W ( h h ) SG F F S S SG F S F With measurement of W, we can obtain Q, Q in real time. F SG Rx F 49

50 Estimation of feedwater flow through the venturi tube : W C F T D p D D 2 4 F d a( F )( ph / 4) (2 F ) /[1 ( ph / F ) ] where F ( T ) a D th F, D F : area factor of the nozzle for thermal expansion : diameters of the throat of the venturi tube and feedwater line C d : discharge coefficient measured at the standard p and T 50

51 Degradation of feedwater flow measurement instrument Copper plate-out problem on the venturi nozzle : Cu oxides and hydroxides from tubes in feedwater heaters and MSR + magnetite (Fe3O4) formed on the nozzle: (CiO) x (Fe 3 O 4 ) y Copper plate-out indicated dp > true dp increase in nozzle surface roughness indicated feedwater flow > true feedwater flow indicated power > true power if indicated power is higher than licensed power, reactor power is reduced reduction of load reduction of electric power 51

52 Solutions maintaining a clean venturi nozzle maintaining an air-tight secondary system and a clean condenser replacing cast-iron nozzle with stainless steel nozzle replacing Cu-containing tubes with stainless steel tubes heat rate monitoring system 52

53 7.3.4 S/G Sizing Cost Analysis : Yearly Cost during Lifetime: C A ( RC E C ) SG a p 1 2 C : yearly cost during life time C a : cost per unit area C p : cost per unit energy E : pumping power per unit area : pump running time n n R : capital recovery factor yearly rate due to depression = i( i 1) /[ 1 i 1] i : interest rate n : steam generator life (yr) 1 : yearly capital cost including interest during life time 2 : yearly operating cost Six-Tenths Rule: C C ( A / A ) a a0 SG SG

54 Pumping power : Pumping Power per Unit Area = head P m / ( A ) P Q / A loss p SG loss SG Note : P Q ( P A ) u F u loss loss f Pressure Loss : head P head loss p ( P P P P ) ( K fl / d K K ) u 2 2 in f bending out in i b out p p Power = Work ( F x) dx F F u dt dt dt 54

55 Wall thickness : Wall thickness by ASME Power Boiler Code Formula: t ( d d ) / 2 p d /(2S 2 yp ) o i p o p where 55

56 S/G Tube Area : Primary and secondary temperature difference at the same axial position : T ( z) T q ( z)( R R R R ) q ( z) R C( q ( z)) p s p m f s pmf 1/3 where 56

57 Temperature decrement between (z+dz) and z : ( T ( z dz) T ) ( T ( z) T ) T ( z dz) T ( z) p s p s p p dt z R C q z dq z 2/3 p( ) [ pmf ( / 3)( ( )) ] ( ) Increment of heat transfer rate between (z+dz) and z: da( z) dq( z) / q ( z) m c dt / q ( z) p p p m c R C q z dq z q z 2/3 p p[ pmf ( / 3)( ( )) ] ( ) / ( ) Integrating da from the inlet and outlet of the tubes yields out in da A Q T T R ln q z C q z 2/3 out SG [ SG / ( pin pout )][ pmf ( ( )) ( / 2)( ( )) ] in f ( Q, T, T, R, q (0), q ( L )] SG pin pout pmf SG 57

58 To get the expression of q'' in terms of temperature we need to solve 3 Rpmf X CX T 0 where X q z T T T 1/3 ( ), p s Solution of the above equation : b 2 3 X a ( a b ) a ( a b ) where a T /(2 R ), b C /(3 R ) pmf pmf

59 local heat flux in terms of parameters: q ( z 0) X g ( T T, R ), pin S pmf q ( z L ) X g ( T T, R ) 3 SG 2 2 pout S pmf Final expression of the total tube area: A f ( Q, T, T, m, R, T or p ) SG SG pin pout p pmf S S 59

60 Design Procedure : Input : Output : Get t and Q, d, T, m, p, p A, L SG o pin p s p d i u p With guessed, the total number of tube : N SG N m u d 2 SG p / ( p p i / 4) SG SG Get Get T, R, q ( z 0), q ( z L ) pout pmf SG A SG and L Get pumping power. SG Other way to det er min e A : A Q / ( U T ) SG SG LN where SG T [( T T ) ( T T )] / ln[( T T ) / ( T T )] LN pin SG pout SG pin SG pout SG Get yearly cost during lifetime. Check whether C is an optimal value or not. Check whether p loss is reasonable or not. 60

Chapter 8. Design of Pressurizer and Plant Control

Chapter 8. Design of Pressurizer and Plant Control Nuclear Systems Design Chapter 8. Design of Pressurizer and Plant Control Prof. Hee Cheon NO 8.1 Sizing Problem of Pressurizer and Plant Control 8.1.1 Basic Plant Control Basic Control Scheme I : to maintain

More information

ATLAS Facility Description Report

ATLAS Facility Description Report KAERI/TR-3754/2009 기술보고서 ATLAS Facility Description Report ATLAS 실험장치기술보고서 한국원자력연구원 제출문 한국원자력연구원장귀하 본보고서를 2009 연도 APR1400/OPR1000 핵심사고열수력종합 효과실험 과제의기술보고서로제출합니다. 2009. 4. 주저자 : 강경호공저자 : 문상기박현식조석최기용 ATLAS

More information

The Research of Heat Transfer Area for 55/19 Steam Generator

The Research of Heat Transfer Area for 55/19 Steam Generator Journal of Power and Energy Engineering, 205, 3, 47-422 Published Online April 205 in SciRes. http://www.scirp.org/journal/jpee http://dx.doi.org/0.4236/jpee.205.34056 The Research of Heat Transfer Area

More information

Chapter 10: Boiling and Condensation 1. Based on lecture by Yoav Peles, Mech. Aero. Nuc. Eng., RPI.

Chapter 10: Boiling and Condensation 1. Based on lecture by Yoav Peles, Mech. Aero. Nuc. Eng., RPI. Chapter 10: Boiling and Condensation 1 1 Based on lecture by Yoav Peles, Mech. Aero. Nuc. Eng., RPI. Objectives When you finish studying this chapter, you should be able to: Differentiate between evaporation

More information

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004)

Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p (July 2004) Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 41, No. 7, p. 765 770 (July 2004) TECHNICAL REPORT Experimental and Operational Verification of the HTR-10 Once-Through Steam Generator (SG) Heat-transfer

More information

Experiment (4): Flow measurement

Experiment (4): Flow measurement Experiment (4): Flow measurement Introduction: The flow measuring apparatus is used to familiarize the students with typical methods of flow measurement of an incompressible fluid and, at the same time

More information

ENGINEERING OF NUCLEAR REACTORS

ENGINEERING OF NUCLEAR REACTORS 22.312 ENGINEERING OF NUCLEAR REACTORS Monday, December 17 th, 2007, 9:00am-12:00 pm FINAL EXAM SOLUTIONS Problem 1 (45%) Analysis of Decay Heat Removal during a Severe Accident i) The energy balance for

More information

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 6

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 6 Lectures on Nuclear Power Safety Lecture No 6 Title: Introduction to Thermal-Hydraulic Analysis of Nuclear Reactor Cores Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture

More information

Structural Health Monitoring of Nuclear Power Plants using Inverse Analysis in Measurements

Structural Health Monitoring of Nuclear Power Plants using Inverse Analysis in Measurements Structural Health Monitoring of Nuclear Power Plants using Inverse Analysis in Measurements Fumio Kojima Organization of Advanced Science and Technology, Kobe University 1-1, Rokkodai, Nada-ku Kobe 657-8501

More information

Turbine Meter TRZ 03 PRODUCT INFORMATION. Reliable Measurement of Gas

Turbine Meter TRZ 03 PRODUCT INFORMATION. Reliable Measurement of Gas Turbine Meter TRZ 0 PRODUCT INFORMATION Reliable Measurement of Gas TURBINE METER TRZ 0 Method of operation, Construction Method of operation The TRZ 0 turbine meter is a flow meter suitable for gas measurement

More information

NPP Simulators for Education Workshop - Passive PWR Models

NPP Simulators for Education Workshop - Passive PWR Models NPP Simulators for Education Workshop - Passive PWR Models Wilson Lam (wilson@cti-simulation.com) CTI Simulation International Corp. www.cti-simulation.com Sponsored by IAEA Learning Objectives Understand

More information

INTRODUCTION: Shell and tube heat exchangers are one of the most common equipment found in all plants. How it works?

INTRODUCTION: Shell and tube heat exchangers are one of the most common equipment found in all plants. How it works? HEAT EXCHANGERS 1 INTRODUCTION: Shell and tube heat exchangers are one of the most common equipment found in all plants How it works? 2 WHAT ARE THEY USED FOR? Classification according to service. Heat

More information

DEVELOPMENT OF COMPUTATIONAL MULTIFLUID DYNAMICS MODELS FOR NUCLEAR REACTOR APPLICATIONS

DEVELOPMENT OF COMPUTATIONAL MULTIFLUID DYNAMICS MODELS FOR NUCLEAR REACTOR APPLICATIONS DEVELOPMENT OF COMPUTATIONAL MULTIFLUID DYNAMICS MODELS FOR NUCLEAR REACTOR APPLICATIONS Henry Anglart Royal Institute of Technology, Department of Physics Division of Nuclear Reactor Technology Stocholm,

More information

Heat Transfer with Phase Change

Heat Transfer with Phase Change CM3110 Transport I Part II: Heat Transfer Heat Transfer with Phase Change Evaporators and Condensers Professor Faith Morrison Department of Chemical Engineering Michigan Technological University 1 Heat

More information

Onset of Flow Instability in a Rectangular Channel Under Transversely Uniform and Non-uniform Heating

Onset of Flow Instability in a Rectangular Channel Under Transversely Uniform and Non-uniform Heating Onset of Flow Instability in a Rectangular Channel Under Transversely Uniform and Non-uniform Heating Omar S. Al-Yahia, Taewoo Kim, Daeseong Jo School of Mechanical Engineering, Kyungpook National University

More information

HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES

HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES HEAT TRANSFER CAPABILITY OF A THERMOSYPHON HEAT TRANSPORT DEVICE WITH EXPERIMENTAL AND CFD STUDIES B.M. Lingade a*, Elizabeth Raju b, A Borgohain a, N.K. Maheshwari a, P.K.Vijayan a a Reactor Engineering

More information

HEAT TRANSFER. Mechanisms of Heat Transfer: (1) Conduction

HEAT TRANSFER. Mechanisms of Heat Transfer: (1) Conduction HEAT TRANSFER Mechanisms of Heat Transfer: (1) Conduction where Q is the amount of heat, Btu, transferred in time t, h k is the thermal conductivity, Btu/[h ft 2 ( o F/ft)] A is the area of heat transfer

More information

Stress and fatigue analyses of a PWR reactor core barrel components

Stress and fatigue analyses of a PWR reactor core barrel components Seite 1 von 10 Stress and fatigue analyses of a PWR reactor core barrel components L. Mkrtchyan, H. Schau, H. Eggers TÜV SÜD ET Mannheim, Germany Abstract: The integrity of the nuclear reactor core barrel

More information

Chapter 4 DYNAMICS OF FLUID FLOW

Chapter 4 DYNAMICS OF FLUID FLOW Faculty Of Engineering at Shobra nd Year Civil - 016 Chapter 4 DYNAMICS OF FLUID FLOW 4-1 Types of Energy 4- Euler s Equation 4-3 Bernoulli s Equation 4-4 Total Energy Line (TEL) and Hydraulic Grade Line

More information

Calculation method for the determination of leak probabilities for complex structural geometries and load conditions

Calculation method for the determination of leak probabilities for complex structural geometries and load conditions 3 Reactor safety research 3.1 Calculation method for the determination of leak probabilities for complex structural geometries and load conditions Dr. Jürgen Sievers Yan Wang When it comes to assessing

More information

Boiling and Condensation (ME742)

Boiling and Condensation (ME742) Indian Institute of Technology Kanpur Department of Mechanical Engineering Boiling and Condensation (ME742) PG/Open Elective Credits: 3-0-0-9 Updated Syllabus: Introduction: Applications of boiling and

More information

Thermal-Hydraulic Design

Thermal-Hydraulic Design Read: BWR Section 3 (Assigned Previously) PWR Chapter (Assigned Previously) References: BWR SAR Section 4.4 PWR SAR Section 4.4 Principal Design Requirements (1) Energy Costs Minimized A) Maximize Plant

More information

Chapter 11: Heat Exchangers. Dr Ali Jawarneh Department of Mechanical Engineering Hashemite University

Chapter 11: Heat Exchangers. Dr Ali Jawarneh Department of Mechanical Engineering Hashemite University Chapter 11: Heat Exchangers Dr Ali Jawarneh Department of Mechanical Engineering Hashemite University Objectives When you finish studying this chapter, you should be able to: Recognize numerous types of

More information

Department of Engineering and System Science, National Tsing Hua University,

Department of Engineering and System Science, National Tsing Hua University, 3rd International Conference on Materials Engineering, Manufacturing Technology and Control (ICMEMTC 2016) The Establishment and Application of TRACE/CFD Model for Maanshan PWR Nuclear Power Plant Yu-Ting

More information

Introduction to Chemical Engineering Thermodynamics. Chapter 7. KFUPM Housam Binous CHE 303

Introduction to Chemical Engineering Thermodynamics. Chapter 7. KFUPM Housam Binous CHE 303 Introduction to Chemical Engineering Thermodynamics Chapter 7 1 Thermodynamics of flow is based on mass, energy and entropy balances Fluid mechanics encompasses the above balances and conservation of momentum

More information

12 Moderator And Moderator System

12 Moderator And Moderator System 12 Moderator And Moderator System 12.1 Introduction Nuclear fuel produces heat by fission. In the fission process, fissile atoms split after absorbing slow neutrons. This releases fast neutrons and generates

More information

DESIGN AND COST ANALYSIS OF HEAT TRANSFER EQUIPMENTS

DESIGN AND COST ANALYSIS OF HEAT TRANSFER EQUIPMENTS DESIGN AND COST ANALYSIS OF HEAT TRANSFER EQUIPMENTS Md. Khairul Islam Lecturer Department of Applied Chemistry and Chemical Engineering. University of Rajshahi. What is design? Design includes all the

More information

FIELD TEST OF WATER-STEAM SEPARATORS FOR THE DSG PROCESS

FIELD TEST OF WATER-STEAM SEPARATORS FOR THE DSG PROCESS FIELD TEST OF WATER-STEAM SEPARATORS FOR THE DSG PROCESS Markus Eck 1, Holger Schmidt 2, Martin Eickhoff 3, Tobias Hirsch 1 1 German Aerospace Center (DLR), Institute of Technical Thermodynamics, Pfaffenwaldring

More information

THERMAL STRATIFICATION MONITORING OF ANGRA 2 STEAM GENERATOR MAIN FEEDWATER NOZZLES

THERMAL STRATIFICATION MONITORING OF ANGRA 2 STEAM GENERATOR MAIN FEEDWATER NOZZLES 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 THERMAL STRATIFICATION

More information

HWR Moderator Sub-cooling Requirements to Demonstrate Back-up Capabilities of Moderator During Accidents

HWR Moderator Sub-cooling Requirements to Demonstrate Back-up Capabilities of Moderator During Accidents HWR Moderator Sub-cooling Requirements to Demonstrate Back-up Capabilities of Moderator During Accidents HEMANT KALRA NPCIL IAEA International Collaboration Standard Problem (ICSP) 1 st Workshop November,

More information

Development of Crud Chemistry Model using MOOSE. Amit Agarwal, Jim Henshaw & John McGurk

Development of Crud Chemistry Model using MOOSE. Amit Agarwal, Jim Henshaw & John McGurk Development of Crud Chemistry Model using MOOSE Amit Agarwal, Jim Henshaw & John McGurk Introduction: MOOSE MOOSE software tool developed by Idaho National Labs MOOSE used for solving partial differential

More information

A Probabilistic Physics-of-Failure Approach to Assessment of Frequency of In-Vessel Steam Generator Tube Rupture Accident in SMRs

A Probabilistic Physics-of-Failure Approach to Assessment of Frequency of In-Vessel Steam Generator Tube Rupture Accident in SMRs A Probabilistic Physics-of-Failure Approach to Assessment of Frequency of In-Vessel Steam Generator Tube Rupture Accident in SMRs Mohammad Modarres Professor of Nuclear Engineering Center for Risk and

More information

The exergy of asystemis the maximum useful work possible during a process that brings the system into equilibrium with aheat reservoir. (4.

The exergy of asystemis the maximum useful work possible during a process that brings the system into equilibrium with aheat reservoir. (4. Energy Equation Entropy equation in Chapter 4: control mass approach The second law of thermodynamics Availability (exergy) The exergy of asystemis the maximum useful work possible during a process that

More information

THESIS. Andrew Jordan Clark, B.S. Graduate Program in Nuclear Engineering. The Ohio State University. Master s Examination Committee:

THESIS. Andrew Jordan Clark, B.S. Graduate Program in Nuclear Engineering. The Ohio State University. Master s Examination Committee: Effectiveness of Surveillance Sampling Strategies for Detecting Steam Generator Tube Degradation THESIS Presented in Partial Fulfillment of the Requirement for the Degree Master of Science in the Graduate

More information

ETA Recovery Process with Ion Exchange and Evaporation

ETA Recovery Process with Ion Exchange and Evaporation ETA Recovery Process with Ion Exchange and Evaporation IN HYOUNG RHEE, HYUN KYOUNG AHN, HYUN JUN JUNG Department of Energy and Environmental Engineering Soonchunhyang University 646 Eupnae-ri Shinchang-myeon

More information

EXPERIMENTAL ANALYSIS OF R-134a FLOW CONDENSATION IN A SMOOTH TUBE

EXPERIMENTAL ANALYSIS OF R-134a FLOW CONDENSATION IN A SMOOTH TUBE HEFAT2012 9 th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics 16 18 July 2012 Malta EXPERIMENTAL ANALYSIS OF R-134a FLOW CONDENSATION IN A SMOOTH TUBE Bastos S., Fernández-Seara

More information

THERMAL HYDRAULIC ANALYSIS IN REACTOR VESSEL INTERNALS CONSIDERING IRRADIATION HEAT

THERMAL HYDRAULIC ANALYSIS IN REACTOR VESSEL INTERNALS CONSIDERING IRRADIATION HEAT THERMAL HYDRAULIC ANALYSIS IN REACTOR VESSEL INTERNALS CONSIDERING IRRADIATION HEAT Sungje Hong, Kunwoo Yi, Jin Huh, Inyoung Im and Eunkee Kim KEPCO Engineering and Construction Company. INC. NSSS Division.

More information

Applied Fluid Mechanics

Applied Fluid Mechanics Applied Fluid Mechanics 1. The Nature of Fluid and the Study of Fluid Mechanics 2. Viscosity of Fluid 3. Pressure Measurement 4. Forces Due to Static Fluid 5. Buoyancy and Stability 6. Flow of Fluid and

More information

A METHOD TO PREVENT SEVERE POWER AND FLOW OSCILLATIONS IN BOILING WATER REACTORS

A METHOD TO PREVENT SEVERE POWER AND FLOW OSCILLATIONS IN BOILING WATER REACTORS A METHOD TO PREVENT SEVERE POWER AND FLOW OSCILLATIONS IN BOILING WATER REACTORS Yousef M. Farawila Farawila et al., Inc. Nuclear@Farawila.com ABSTRACT This paper introduces a new method for preventing

More information

Applied Fluid Mechanics

Applied Fluid Mechanics Applied Fluid Mechanics 1. The Nature of Fluid and the Study of Fluid Mechanics 2. Viscosity of Fluid 3. Pressure Measurement 4. Forces Due to Static Fluid 5. Buoyancy and Stability 6. Flow of Fluid and

More information

Stratification issues in the primary system. Review of available validation experiments and State-of-the-Art in modelling capabilities.

Stratification issues in the primary system. Review of available validation experiments and State-of-the-Art in modelling capabilities. Stratification issues in the primary system. Review of available validation experiments and State-of-the-Art in modelling capabilities. (StratRev) NKS seminar, Armémuseum, 2009-03-26 Johan Westin and Mats

More information

3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading

3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading E-Journal of Advanced Maintenance Vol.9-2 (2017) 84-90 Japan Society of Maintenology 3D CFD and FEM Evaluations of RPV Stress Intensity Factor during PTS Loading Xiaoyong Ruan 1,*, Toshiki Nakasuji 1 and

More information

Steam Generator Tubing Inspection

Steam Generator Tubing Inspection Steam Generator Tubing Inspection Analytical Determination of Critical Flaw Dimensions in Steam Generator Tubing I. Kadenko, N. Sakhno, R. Yermolenko, Nondestructive Examination Training and Certification

More information

first law of ThermodyNamics

first law of ThermodyNamics first law of ThermodyNamics First law of thermodynamics - Principle of conservation of energy - Energy can be neither created nor destroyed Basic statement When any closed system is taken through a cycle,

More information

Experiment No.4: Flow through Venturi meter. Background and Theory

Experiment No.4: Flow through Venturi meter. Background and Theory Experiment No.4: Flow through Venturi meter Background and Theory Introduction Flow meters are used in the industry to measure the volumetric flow rate of fluids. Differential pressure type flow meters

More information

EFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION

EFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION EFFECT OF DISTRIBUTION OF VOLUMETRIC HEAT GENERATION ON MODERATOR TEMPERATURE DISTRIBUTION A. K. Kansal, P. Suryanarayana, N. K. Maheshwari Reactor Engineering Division, Bhabha Atomic Research Centre,

More information

EddyMax Tube Inspection

EddyMax Tube Inspection EddyMax Tube Inspection Client: Client a Facility: site b Items Inspected: Inlet Heater Inspection Method: Eddy Current Tube Inspection Commencement Date: 28 th June 2016 Completion Date: 29 th June 2016

More information

Laboratory 12: Three Thermodynamics Experiments

Laboratory 12: Three Thermodynamics Experiments Laboratory 12: Three Thermodynamics Experiments Experiment 1: Coefficient of Linear Expansion of Metals The fact that most objects expand when heated is common knowledge. The change in the linear dimensions

More information

Name: 10/21/2014. NE 161 Midterm. Multiple choice 1 to 10 are 2 pts each; then long problems 1 through 4 are 20 points each.

Name: 10/21/2014. NE 161 Midterm. Multiple choice 1 to 10 are 2 pts each; then long problems 1 through 4 are 20 points each. NE 161 Midterm Multiple choice 1 to 10 are 2 pts each; then long problems 1 through 4 are 20 points each. 1. Which would have a higher mass flow rate out of a 1 ft 2 break, a. 200 psia subcooled water

More information

CHAPTER 5 MASS AND ENERGY ANALYSIS OF CONTROL VOLUMES

CHAPTER 5 MASS AND ENERGY ANALYSIS OF CONTROL VOLUMES Thermodynamics: An Engineering Approach 8th Edition in SI Units Yunus A. Çengel, Michael A. Boles McGraw-Hill, 2015 CHAPTER 5 MASS AND ENERGY ANALYSIS OF CONTROL VOLUMES Lecture slides by Dr. Fawzi Elfghi

More information

HEAT TRANSFER ENHANCEMENT IN HEAT EXCHANGER USING TANGENTIAL INJECTOR TYPE SWIRL GENERATOR

HEAT TRANSFER ENHANCEMENT IN HEAT EXCHANGER USING TANGENTIAL INJECTOR TYPE SWIRL GENERATOR HEAT TRANSFER ENHANCEMENT IN HEAT EXCHANGER USING TANGENTIAL INJECTOR TYPE SWIRL GENERATOR Hanumant Jagdale Department of Mechanical Engineering, MIT, Aurangabad, India Subhash Lahane Department of Mechanical

More information

CFD STUDIES IN THE PREDICTION OF THERMAL STRIPING IN AN LMFBR

CFD STUDIES IN THE PREDICTION OF THERMAL STRIPING IN AN LMFBR CFD STUDIES IN THE PREDICTION OF THERMAL STRIPING IN AN LMFBR K. Velusamy, K. Natesan, P. Selvaraj, P. Chellapandi, S. C. Chetal, T. Sundararajan* and S. Suyambazhahan* Nuclear Engineering Group Indira

More information

T718. c Dr. Md. Zahurul Haq (BUET) HX: Energy Balance and LMTD ME 307 (2018) 2/ 21 T793

T718. c Dr. Md. Zahurul Haq (BUET) HX: Energy Balance and LMTD ME 307 (2018) 2/ 21 T793 HX: Energy Balance and LMTD Dr. Md. Zahurul Haq Professor Department of Mechanical Engineering Bangladesh University of Engineering & Technology (BUET) Dhaka-000, Bangladesh http://zahurul.buet.ac.bd/

More information

THE EFFECT OF TWO PHASE (AIR-WATER) FLOW CHARACTERISTICS ON MOMENTUM FLUX DUE TO FLOW TURNING ELEMENTS AT ATMOSPHERIC CONDITIONS

THE EFFECT OF TWO PHASE (AIR-WATER) FLOW CHARACTERISTICS ON MOMENTUM FLUX DUE TO FLOW TURNING ELEMENTS AT ATMOSPHERIC CONDITIONS International Journal of Latest Trends in Engineering and Technology Vol.(8)Issue(1), pp.319-328 DOI: http://dx.doi.org/10.21172/1.81.041 e-issn:2278-621x AN EXPERIMENTAL STUDY OF THE EFFECT OF TWO PHASE

More information

Fluid Flow, Heat Transfer and Boiling in Micro-Channels

Fluid Flow, Heat Transfer and Boiling in Micro-Channels L.P. Yarin A. Mosyak G. Hetsroni Fluid Flow, Heat Transfer and Boiling in Micro-Channels 4Q Springer 1 Introduction 1 1.1 General Overview 1 1.2 Scope and Contents of Part 1 2 1.3 Scope and Contents of

More information

THE CERN CRYOGENIC TEST FACILITY FOR THE ATLAS BARREL TOROID MAGNETS

THE CERN CRYOGENIC TEST FACILITY FOR THE ATLAS BARREL TOROID MAGNETS EUROPEAN ORGANIZATION FOR NUCLEAR RESEARCH European Laboratory for Particle Physics Large Hadron Collider Project LHC Project Report 365 THE CERN CRYOGENIC TEST FACILITY FOR THE ATLAS BARREL TOROID MAGNETS

More information

Fuel - Coolant Heat Transfer

Fuel - Coolant Heat Transfer Heat Transfer 5-1 Chapter 5 Fuel - Coolant Heat Transfer 5.1 Introduction The interface between the fuel and the coolant is centrally important to reactor design since it is here that the limit to power

More information

Heat processes. Heat exchange

Heat processes. Heat exchange Heat processes Heat exchange Heat energy transported across a surface from higher temperature side to lower temperature side; it is a macroscopic measure of transported energies of molecular motions Temperature

More information

The Dynamical Loading of the WWER440/V213 Reactor Pressure Vessel Internals during LOCA Accident in Hot and Cold Leg of the Primary Circuit

The Dynamical Loading of the WWER440/V213 Reactor Pressure Vessel Internals during LOCA Accident in Hot and Cold Leg of the Primary Circuit The Dynamical Loading of the WWER440/V213 Reactor Pressure Vessel Internals during LOCA Accident in Hot and Cold Leg of the Primary Circuit ABSTRACT Peter Hermansky, Marian Krajčovič VUJE, Inc. Okružná

More information

Ways to Improve the Energy Efficiency of AN Solution Plants

Ways to Improve the Energy Efficiency of AN Solution Plants Ways to Improve the Energy Efficiency of AN Solution Plants by Axel Erben Uhde GmbH Dortmund, Germany Prepared for Presentation at NITROGEN 2009 International Conference Rome, Italy 22-25 February 2009

More information

heat transfer process where a liquid undergoes a phase change into a vapor (gas)

heat transfer process where a liquid undergoes a phase change into a vapor (gas) Two-Phase: Overview Two-Phase two-phase heat transfer describes phenomena where a change of phase (liquid/gas) occurs during and/or due to the heat transfer process two-phase heat transfer generally considers

More information

UPDATES ON DESIGN AND ANALYSES OF THE PLATE-TYPE DIVERTOR

UPDATES ON DESIGN AND ANALYSES OF THE PLATE-TYPE DIVERTOR UPDATES ON DESIGN AND ANALYSES OF THE PLATE-TYPE DIVERTOR X.R. Wang 1, S. Malang 2, M. S. Tillack 1 1 University of California, San Diego, CA 2 Fusion Nuclear Technology Consulting, Germany ARIES-Pathways

More information

ME 331 Homework Assignment #6

ME 331 Homework Assignment #6 ME 33 Homework Assignment #6 Problem Statement: ater at 30 o C flows through a long.85 cm diameter tube at a mass flow rate of 0.020 kg/s. Find: The mean velocity (u m ), maximum velocity (u MAX ), and

More information

Instability Analysis in Peach Bottom NPP Using a Whole Core Thermalhydraulic-Neutronic Model with RELAP5/PARCS v2.7

Instability Analysis in Peach Bottom NPP Using a Whole Core Thermalhydraulic-Neutronic Model with RELAP5/PARCS v2.7 Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol., pp.10-18 (011) ARTICLE Instability Analysis in Peach Bottom NPP Using a Whole Core Thermalhydraulic-Neutronic Model with RELAP/PARCS v. Agustín ABARCA,

More information

Heat and Mass Transfer Unit-1 Conduction

Heat and Mass Transfer Unit-1 Conduction 1. State Fourier s Law of conduction. Heat and Mass Transfer Unit-1 Conduction Part-A The rate of heat conduction is proportional to the area measured normal to the direction of heat flow and to the temperature

More information

Entropy and the Second Law of Thermodynamics

Entropy and the Second Law of Thermodynamics Entropy and the Second Law of Thermodynamics Reading Problems 7-1 7-3 7-88, 7-131, 7-135 7-6 7-10 8-24, 8-44, 8-46, 8-60, 8-73, 8-99, 8-128, 8-132, 8-1 8-10, 8-13 8-135, 8-148, 8-152, 8-166, 8-168, 8-189

More information

Performance Tests for an All-welded Plate Heat Exchanger Liang Huang1,a, Bingcheng Liu1,b and Qingling Li1,c

Performance Tests for an All-welded Plate Heat Exchanger Liang Huang1,a, Bingcheng Liu1,b and Qingling Li1,c 4th International Conference on Machinery, Materials and Computing Technology (ICMMCT 216) Performance Tests for an All-welded Plate Heat Exchanger Liang Huang1,a, Bingcheng Liu1,b and Qingling Li1,c 1

More information

Effect of ph and Temperature on Condensation and dissolution

Effect of ph and Temperature on Condensation and dissolution Proceedings of the 6th WSEAS International Conference on Signal Processing, Robotics and Automation, Corfu Island, Greece, February 16-19, 2007 288 Effect of ph and Temperature on Condensation and dissolution

More information

DETERMINATION OF R134A S CONVECTIVE HEAT TRANSFER COEFFICIENT IN HORIZONTAL EVAPORATORS HAVING SMOOTH AND CORRUGATED TUBES

DETERMINATION OF R134A S CONVECTIVE HEAT TRANSFER COEFFICIENT IN HORIZONTAL EVAPORATORS HAVING SMOOTH AND CORRUGATED TUBES DETERMINATION OF R134A S CONVECTIVE HEAT TRANSFER COEFFICIENT IN HORIZONTAL EVAPORATORS HAVING SMOOTH AND CORRUGATED TUBES A.S. Dalkilic, Heat Thermodynamics Division, Department of Mechanical Engineering,

More information

10 minutes reading time is allowed for this paper.

10 minutes reading time is allowed for this paper. EGT1 ENGINEERING TRIPOS PART IB Tuesday 31 May 2016 2 to 4 Paper 4 THERMOFLUID MECHANICS Answer not more than four questions. Answer not more than two questions from each section. All questions carry the

More information

Introduction to Heat and Mass Transfer. Week 14

Introduction to Heat and Mass Transfer. Week 14 Introduction to Heat and Mass Transfer Week 14 Next Topic Internal Flow» Velocity Boundary Layer Development» Thermal Boundary Layer Development» Energy Balance Velocity Boundary Layer Development Velocity

More information

GRAVITY EFFECT ON THE DISTRIBUTION OF REFRIGERANT FLOW IN A MULTI-CIRCUITED CONDENSER

GRAVITY EFFECT ON THE DISTRIBUTION OF REFRIGERANT FLOW IN A MULTI-CIRCUITED CONDENSER Proceedings of Fifth International Conference on Enhanced, Compact and Ultra-Compact Heat Exchangers: Science, Engineering and Technology, Eds. R.K. Shah, M. Ishizuka, T.M. Rudy, and V.V. Wadekar, Engineering

More information

BOILING AND CONDENSATION HEAT TRANSFER COEFFICIENTS FOR A HEAT PIPE HEAT EXCHANGER

BOILING AND CONDENSATION HEAT TRANSFER COEFFICIENTS FOR A HEAT PIPE HEAT EXCHANGER Frontiers in Heat Pipes Available at www.thermalfluidscentral.org BOILING AND CONDENSATION HEAT TRANSFER COEFFICIENTS FOR A HEAT PIPE HEAT EXCHANGER R. Laubscher, R.T. Dobson * Department of Mechanical

More information

Attempt ALL QUESTIONS IN SECTION A and ANY TWO QUESTIONS IN SECTION B Linear graph paper will be provided.

Attempt ALL QUESTIONS IN SECTION A and ANY TWO QUESTIONS IN SECTION B Linear graph paper will be provided. UNIVERSITY OF EAST ANGLIA School of Mathematics Main Series UG Examination 2013-2014 ENGINEERING PRINCIPLES AND LAWS ENG-4002Y Time allowed: 3 Hours Attempt ALL QUESTIONS IN SECTION A and ANY TWO QUESTIONS

More information

Water Chemistry. Program Overview

Water Chemistry. Program Overview Water Chemistry Program Description Program Overview Water chemistry conditions at nuclear power plants can impact corrosion rates, fuel performance, and radiation management. In light of increasing demands

More information

FE Fluids Review March 23, 2012 Steve Burian (Civil & Environmental Engineering)

FE Fluids Review March 23, 2012 Steve Burian (Civil & Environmental Engineering) Topic: Fluid Properties 1. If 6 m 3 of oil weighs 47 kn, calculate its specific weight, density, and specific gravity. 2. 10.0 L of an incompressible liquid exert a force of 20 N at the earth s surface.

More information

Department of Energy Fundamentals Handbook. THERMODYNAMICS, HEAT TRANSFER, AND FLUID FLOW, Module 3 Fluid Flow

Department of Energy Fundamentals Handbook. THERMODYNAMICS, HEAT TRANSFER, AND FLUID FLOW, Module 3 Fluid Flow Department of Energy Fundamentals Handbook THERMODYNAMICS, HEAT TRANSFER, AND FLUID FLOW, Module 3 REFERENCES REFERENCES Streeter, Victor L., Fluid Mechanics, 5th Edition, McGraw-Hill, New York, ISBN 07-062191-9.

More information

Liquid Feed Injection in a High Density Riser

Liquid Feed Injection in a High Density Riser Refereed Proceedings The 12th International Conference on Fluidization - New Horizons in Fluidization Engineering Engineering Conferences International Year 2007 Liquid Feed Injection in a High Density

More information

Vacuum Pumps. Two general classes exist: Gas transfer physical removal of matter. Mechanical, diffusion, turbomolecular

Vacuum Pumps. Two general classes exist: Gas transfer physical removal of matter. Mechanical, diffusion, turbomolecular Vacuum Technology Vacuum Pumps Two general classes exist: Gas transfer physical removal of matter Mechanical, diffusion, turbomolecular Adsorption entrapment of matter Cryo, sublimation, ion Mechanical

More information

EFFECTS OF COATING STRUCTURE BY Al 2 O 3 NANOPARTICLES DEPOSITION ON CRITICAL HEAT FLUX OF R123 IN FLOW BOILING

EFFECTS OF COATING STRUCTURE BY Al 2 O 3 NANOPARTICLES DEPOSITION ON CRITICAL HEAT FLUX OF R123 IN FLOW BOILING EFFECTS OF COATING STRUCTURE BY Al 2 O 3 NANOPARTICLES DEPOSITION ON CRITICAL HEAT FLUX OF R123 IN FLOW BOILING Seok Bin Seo and In Cheol Bang School of Mechanical and Nuclear Engineering Ulsan National

More information

Applied Thermodynamics for Marine Systems Prof. P. K. Das Department of Mechanical Engineering Indian Institute of Technology, Kharagpur

Applied Thermodynamics for Marine Systems Prof. P. K. Das Department of Mechanical Engineering Indian Institute of Technology, Kharagpur Applied Thermodynamics for Marine Systems Prof. P. K. Das Department of Mechanical Engineering Indian Institute of Technology, Kharagpur Lecture No - 03 First Law of Thermodynamics (Open System) Good afternoon,

More information

23 1 TYPES OF HEAT EXCHANGERS

23 1 TYPES OF HEAT EXCHANGERS cen5426_ch23.qxd /26/04 9:42 AM Page 032 032 FUNDAMENTALS OF THERMAL-FLUID SCIENCES 23 TYPES OF HEAT EXCHANGERS Different heat transfer applications require different types of hardware different configurations

More information

Fluid Mechanics. du dy

Fluid Mechanics. du dy FLUID MECHANICS Technical English - I 1 th week Fluid Mechanics FLUID STATICS FLUID DYNAMICS Fluid Statics or Hydrostatics is the study of fluids at rest. The main equation required for this is Newton's

More information

Lecture 13 Flow Measurement in Pipes. I. Introduction

Lecture 13 Flow Measurement in Pipes. I. Introduction Lecture 13 Flow Measurement in Pipes I. Introduction There are a wide variety of methods for measuring discharge and velocity in pipes, or closed conduits Many of these methods can provide very accurate

More information

The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA)

The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA) Nuclear Engineering and Design 186 (1998) 177 11 The three-level scaling approach with application to the Purdue University Multi-Dimensional Integral Test Assembly (PUMA) M. Ishii a, *, S.T. Revankar

More information

Index 741. gas separation 307 Gas-film drag force 88 Gravitational flooding 479 grid sizes 210

Index 741. gas separation 307 Gas-film drag force 88 Gravitational flooding 479 grid sizes 210 Index absolute coordinates 381 ACOPO 515 act of fission 1 Active nucleation seeds at the surface 269 ALPHA 447 alpha-zirconium 605 Aluminum 617 Aluminum oxide 627 annular flow 79 Antivibration bar 296

More information

Safety analysis on beam dump Luca de Ruvo LNL - INFN Safety group SSTAC meeting, July 23, 2015

Safety analysis on beam dump Luca de Ruvo LNL - INFN Safety group SSTAC meeting, July 23, 2015 Safety analysis on beam dump Luca de Ruvo LNL - INFN Safety group SSTAC meeting, July 23, 2015 Topics: 1. Overview on Beam Dump 2. Description of cooling circuit 3. Safety philosofy 4. BD safety system:

More information

A Study on Hydraulic Resistance of Porous Media Approach for CANDU-6 Moderator Analysis

A Study on Hydraulic Resistance of Porous Media Approach for CANDU-6 Moderator Analysis Proceedings of the Korean Nuclear Society Spring Meeting Kwangju, Korea, May 2002 A Study on Hydraulic Resistance of Porous Media Approach for CANDU-6 Moderator Analysis Churl Yoon, Bo Wook Rhee, and Byung-Joo

More information

FINITE ELEMENT COUPLED THERMO-MECHANICAL ANALYSIS OF THERMAL STRATIFICATION OF A NPP STEAM GENERATOR INJECTION NOZZLE

FINITE ELEMENT COUPLED THERMO-MECHANICAL ANALYSIS OF THERMAL STRATIFICATION OF A NPP STEAM GENERATOR INJECTION NOZZLE Proceedings of COBEM 2007 Copyright 2007 by ABCM 19th International Congress of Mechanical Engineering November 5-9, 2007, Brasília, DF FINITE ELEMENT COUPLED THERMO-MECHANICAL ANALYSIS OF THERMAL STRATIFICATION

More information

September 9, The meeting was noticed on July 24, 2014 (ML14206A735). The meeting attendance list is provided in Enclosure 1.

September 9, The meeting was noticed on July 24, 2014 (ML14206A735). The meeting attendance list is provided in Enclosure 1. September 9, 2014 MEMORANDUM TO: Anthony Hsia, Deputy Director Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards FROM: Kristina L. Banovac, Project Manager

More information

English text only NUCLEAR ENERGY AGENCY COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLATIONS

English text only NUCLEAR ENERGY AGENCY COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLATIONS Unclassified NEA/CSNI/R(2008)6/VOL2 NEA/CSNI/R(2008)6/VOL2 Unclassified Organisation de Coopération et de Développement Économiques Organisation for Economic Co-operation and Development 26-Nov-2008 English

More information

Convective Mass Transfer

Convective Mass Transfer Convective Mass Transfer Definition of convective mass transfer: The transport of material between a boundary surface and a moving fluid or between two immiscible moving fluids separated by a mobile interface

More information

CHAPTER 3 BASIC EQUATIONS IN FLUID MECHANICS NOOR ALIZA AHMAD

CHAPTER 3 BASIC EQUATIONS IN FLUID MECHANICS NOOR ALIZA AHMAD CHAPTER 3 BASIC EQUATIONS IN FLUID MECHANICS 1 INTRODUCTION Flow often referred as an ideal fluid. We presume that such a fluid has no viscosity. However, this is an idealized situation that does not exist.

More information

ME 2322 Thermodynamics I PRE-LECTURE Lesson 23 Complete the items below Name:

ME 2322 Thermodynamics I PRE-LECTURE Lesson 23 Complete the items below Name: Lesson 23 1. (10 pt) Write the equation for the thermal efficiency of a Carnot heat engine below: 1 L H 2. (10 pt) Can the thermal efficiency of an actual engine ever exceed that of an equivalent Carnot

More information

PREDICTION OF MASS FLOW RATE AND PRESSURE DROP IN THE COOLANT CHANNEL OF THE TRIGA 2000 REACTOR CORE

PREDICTION OF MASS FLOW RATE AND PRESSURE DROP IN THE COOLANT CHANNEL OF THE TRIGA 2000 REACTOR CORE PREDICTION OF MASS FLOW RATE AND PRESSURE DROP IN THE COOLANT CHANNEL OF THE TRIGA 000 REACTOR CORE Efrizon Umar Center for Research and Development of Nuclear Techniques (P3TkN) ABSTRACT PREDICTION OF

More information

1/54 Circulation pump, safety valve, expansion vessel

1/54 Circulation pump, safety valve, expansion vessel 1/54 Circulation pump, safety valve, expansion vessel pressure loss efficiency of pump secured heat output safety valve sizing expansion vessel sizing Circulation pump 2/54 similar principle as for heating

More information

Heat Tracing Basics. By: Homi R. Mullan 1

Heat Tracing Basics. By: Homi R. Mullan 1 Heat Tracing Basics By: Homi R. Mullan 1 Heat Tracing Basics Topics of Discussion What is Heat Tracing? Why Heat Tracing? Fundamentals of Heat Loss and Heat Replenishment Rules to Remember in the Heat

More information

Principles of Food and Bioprocess Engineering (FS 231) Problems on Heat Transfer

Principles of Food and Bioprocess Engineering (FS 231) Problems on Heat Transfer Principles of Food and Bioprocess Engineering (FS 1) Problems on Heat Transfer 1. What is the thermal conductivity of a material 8 cm thick if the temperature at one end of the product is 0 C and the temperature

More information

ELEC9712 High Voltage Systems. 1.2 Heat transfer from electrical equipment

ELEC9712 High Voltage Systems. 1.2 Heat transfer from electrical equipment ELEC9712 High Voltage Systems 1.2 Heat transfer from electrical equipment The basic equation governing heat transfer in an item of electrical equipment is the following incremental balance equation, with

More information

A VALIDATION OF WESTINGHOUSE MECHANISTIC AND EMPIRICAL DRYOUT PREDICTION METHODS UNDER REALISTIC BWR TRANSIENT CONDITIONS

A VALIDATION OF WESTINGHOUSE MECHANISTIC AND EMPIRICAL DRYOUT PREDICTION METHODS UNDER REALISTIC BWR TRANSIENT CONDITIONS A VALIDATION OF WESTINGHOUSE MECHANISTIC AND EMPIRICAL DRYOUT PREDICTION METHODS UNDER REALISTIC BWR TRANSIENT CONDITIONS O. Puebla Garcia * Royal Institute of Technology 10691, Stockholm, Sweden opuebla@deloitte.es

More information