Lesson 9: Multiplying Media (Reactors)

Size: px
Start display at page:

Download "Lesson 9: Multiplying Media (Reactors)"

Transcription

1 Lesson 9: Multiplying Media (Reactors) Laboratory for Reactor Physics and Systems Behaviour Multiplication Factors Reactor Equation for a Bare, Homogeneous Reactor Geometrical, Material Buckling Spherical, Slab Reactors Cylindrical Reactor Absolute Value of Flux Maximum- to-average Flux Ratio Comments on Criticality Condition Multiplying Media.. 1

2 Media Containing Fuel Neutron propagation considered in passive media till now Characterised by Σ a, Σ t (or Σ s ), External neutron source(s) For a medium containing fissile material, one has a source per unit volume: arising from fissions Here, Q f is not a part of the data provided, but rather is dependent on the flux, i.e. on the sought solution itself The neutronics description yields one or several homogeneous equations Stationary solution exists only if a certain criticality condition is satisfied by the geometrical and material characteristics of the system Multiplying Media.. 2

3 Media Containing Fuel (contd.) For the critical state: productions = absorptions + leakage Condition ~ independent of the flux (all three reaction rates vary in about the same proportions) We will first consider a reactor which is homogeneous and bare Isolated zone, without a reflector or a blanket (i.e. just the core ) Treatment will first be one-group Monoenergetic neutrons (e.g. thermal with appropriately averaged cross-sections) Later will be considered Multizone reactors (e.g. with a reflector, i.e. an outer zone of pure moderator) Multigroup theory (basis used, in most practical cases, for numerical calculations) Certain aspects of the heterogeneity of the reactor lattice (heterogeneous unit-cell: fuel/moderator/ ) Multiplying Media.. 3

4 Multiplication Factors For the infinite medium, in general Multiplying Media.. 4

5 Multiplication Factors (contd.) η c fuel multiplication factor f utilisation factor (for the homogeneous mixture) Laboratory for Reactor Physics and Systems Behaviour For a heterogeneous unit-cell, one needs to consider that the flux is depressed within the fuel region Multiplying Media.. 5

6 System of Finite Size For the infinite medium: k = η c. f This corresponds to k = η c. f. ε. p, with ε = p = 1 All the neutrons have the same energy There are neither resonance absorptions, nor fast fissions For the finite system, one has the effective multiplication factor Multiplying Media.. 6

7 System of Finite Size (contd.) Laboratory for Reactor Physics and Systems Behaviour Three cases to be considered: k eff = 1 critical reactor (self-sustaining chain reaction, constant flux) k eff > 1 supercritical reactor (divergent reaction, increasing flux) k eff < 1 subcritical reactor (convergent reaction, decreasing flux) k eff most important single parameter for the functioning of a reactor Important to note: k eff < k < η c < ν Multiplying Media.. 7

8 Equation for the Critical Reactor Laboratory for Reactor Physics and Systems Behaviour One uses the 1-group diffusion equation for the stationary case (critical reactor) Thereby: Thus, with One-group Reactor Equation Eqn. homogeneous Can be solved for a given geometry, Condition to be satisfied can be identified Simplest systems homogeneous spherical reactor, slab reactor Material Buckling (depends only material properties) Multiplying Media.. 8

9 Spherical Reactor One has (positive sign, cf. passive medium with point source), i.e. For the finite system: 1. Φ at ρ = 0 C = 0 2. Φ = 0 at ρ = R+d = R+ 0.71λ t, i.e. sin {B m (R+d)} = 0 Multiplying Media.. 9

10 Spherical Reactor (contd.) From the condition sin {B m (R+d)} = 0 : For the critical reactor, only i = 1 is valid Smallest eigenvalue Fundamental Mode Other solutions: higher harmonics Exist only in a subcritical system E.g. near the external source B m = B i = iπ R + d for i = 1, 2, Critical condition for the spherical reactor is thus: Multiplying Media.. 10

11 Spherical Reactor (contd.2) The flux distribution is: For a given medium (specific values of criticality condition Critical radius: ), R is determined by the Critical mass: Conversely, if the size (R) is fixed, the material properties need to be identified which yield the appropriate (material buckling) E.g. adjust the enrichment, i.e. k Multiplying Media.. 11

12 Comments For a bare homogeneous reactor, the criticality condition demands an eigenvalue search for the reactor equation: Eigenvalues need to go to zero at the extrapolated outer surface The square of the smallest eigenvalue: B 2 (geometrical buckling) Criticality condition: Flux distribution: proportional to the eigenfunction corresponding to B 2 Absolute level of the flux not yet known A constant ( A, in the example considered) remains undetermined, depends on the power (determined, in turn, by technological constraints ) allows us to determine the criticality condition and the spatial distribution of the flux, but does not fix the latter s absolute value Multiplying Media.. 12

13 Slab Reactor System infinite in the X, Y directions Height H Flux, function only of z Reactor Equation: General solution: Flux, symmetric relative to plane z = 0 ( dφ/dz = 0 at z = 0 ) C = 0 Multiplying Media.. 13

14 Slab Reactor (contd.) Thus, Condition Φ = 0 at yields as eigenvalues: with Square of the smallest eigenvalue ( i = 0 ) (geometrical buckling) Flux distribution: Multiplying Media.. 14

15 Cylindical Reactor For a cylindrical reactor of height H and radius a, Critical Reactor Equation: With the asumption, Multiplying Media.. 15

16 Cylindical Reactor (contd.) Multiplying Media.. 16

17 Cylindical Reactor (contd.2) Comments: The criticality condition implies: (i) If H is so small that, even a does not suffice System remains subcritical (ii) Similarly, if a is too small, Even with H, Multiplying Media.. 17

18 Cylindical Reactor (contd.3) (iii) There are minimal values for H, a (iv) Many combinations of H, a for the critical state - Shaded area corresponds to supercritical states (e.g. power reactor at start-of-cycle ) Multiplying Media.. 18

19 Absolute Flux value For a spherical reactor, if one neglects d extrapolated radius Constant A is determined by the reactor power watts joules/fission Multiplying Media.. 19

20 Absolute Flux value (contd.) For a slab reactor with Per cm 2 of the slab, watts/cm 2 For a cylindrical reactor, one can show: Multiplying Media.. 20

21 ( Φ max / Φ ) Ratio The flux distribution determines the power distribution Reactor homogeneous constant Σ f The maximum-to-average ratio, same for flux, power For bare, homogeneous reactors, flux always maximum at centre, varies strongly (goin to zero at extrapolated surface) In practice, one has a reflector and/ or several different zones in the reactor, which render the flux distribution flatter Multiplying Media.. 21

22 ( Φ max / Φ ) Ratio (Examples) Laboratory for Reactor Physics and Systems Behaviour Spherical Reactor Slab Reactor Multiplying Media.. 22

23 Comments on Criticality Condition Laboratory for Reactor Physics and Systems Behaviour (a) Rewriting above equation: (1) Previously, one had : (2) From (1) (criticality condition): (3) Comparing (2), (3): Multiplying Media.. 23

24 Comments on Criticality Condition (contd.) (b) In general, for given values of k, B 2 : (system either subctritical or supercritical) One may nevertheless use the formalism of a critical system (stationary flux) - We consider a fictitious medium in which the number of n s produced per fission For this medium, yields (criticality condition) For the actual system, one needs to search for the modification which leads to. - Change in B 2 or in k. For a bare homogeneous reactor, the search is direct For a multizone system (heterogeneous layout), one needs to adopt an iterative approach - The dimensions (or the material characteristics) are varied until. Multiplying Media.. 24

25 Comments on Criticality Condition (contd.) (c) We have Laboratory for Reactor Physics and Systems Behaviour Comparing this with: Leakage term DB 2 is like a supplementary Σ a One may consider a reactor of finite dimensions (with a geometrical buckling of B 2 ), as though it were an infinite medium with a poisoning of (However, reactor equation still needs to be solved for obtaining B 2 ) Multiplying Media.. 25

26 Summary, Lesson 9 Multiplying media, multiplication factors 1-group, diffusion equation (Reactor Eq.) Material and geometrical buckling Bare homogeneous reactors (sphere, slab, cylinder, etc.) Absolute flux and reactor power Maximum- to-average flux ratio Comments on criticality condition Non-leakage probability, criticality search, leakage as absorptions (DB 2 ) Multiplying Media.. 26

Lesson 6: Diffusion Theory (cf. Transport), Applications

Lesson 6: Diffusion Theory (cf. Transport), Applications Lesson 6: Diffusion Theory (cf. Transport), Applications Transport Equation Diffusion Theory as Special Case Multi-zone Problems (Passive Media) Self-shielding Effects Diffusion Kernels Typical Values

More information

Lesson 8: Slowing Down Spectra, p, Fermi Age

Lesson 8: Slowing Down Spectra, p, Fermi Age Lesson 8: Slowing Down Spectra, p, Fermi Age Slowing Down Spectra in Infinite Homogeneous Media Resonance Escape Probability ( p ) Resonance Integral ( I, I eff ) p, for a Reactor Lattice Semi-empirical

More information

Lecture 20 Reactor Theory-V

Lecture 20 Reactor Theory-V Objectives In this lecture you will learn the following We will discuss the criticality condition and then introduce the concept of k eff.. We then will introduce the four factor formula and two group

More information

X. Assembling the Pieces

X. Assembling the Pieces X. Assembling the Pieces 179 Introduction Our goal all along has been to gain an understanding of nuclear reactors. As we ve noted many times, this requires knowledge of how neutrons are produced and lost.

More information

X. Neutron and Power Distribution

X. Neutron and Power Distribution X. Neutron and Power Distribution X.1. Distribution of the Neutron Flux in the Reactor In order for the power generated by the fission reactions to be maintained at a constant level, the fission rate must

More information

Nuclear Fission. 1/v Fast neutrons. U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b.

Nuclear Fission. 1/v Fast neutrons. U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b. Nuclear Fission 1/v Fast neutrons should be moderated. 235 U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b. Fission Barriers 1 Nuclear Fission Q for 235 U + n 236 U

More information

2. The Steady State and the Diffusion Equation

2. The Steady State and the Diffusion Equation 2. The Steady State and the Diffusion Equation The Neutron Field Basic field quantity in reactor physics is the neutron angular flux density distribution: Φ( r r, E, r Ω,t) = v(e)n( r r, E, r Ω,t) -- distribution

More information

VIII. Neutron Moderation and the Six Factors

VIII. Neutron Moderation and the Six Factors Introduction VIII. Neutron Moderation and the Six Factors 130 We continue our quest to calculate the multiplication factor (keff) and the neutron distribution (in position and energy) in nuclear reactors.

More information

NUCLEAR SCIENCE ACAD BASIC CURRICULUM CHAPTER 5 NEUTRON LIFE CYCLE STUDENT TEXT REV 2. L th. L f U-235 FUEL MODERATOR START CYCLE HERE THERMAL NEUTRON

NUCLEAR SCIENCE ACAD BASIC CURRICULUM CHAPTER 5 NEUTRON LIFE CYCLE STUDENT TEXT REV 2. L th. L f U-235 FUEL MODERATOR START CYCLE HERE THERMAL NEUTRON ACAD BASIC CURRICULUM NUCLEAR SCIENCE CHAPTER 5 NEUTRON LIFE CYCLE 346 RESONANCE LOSSES p 038 THERMAL NEUTRON 2 THERMAL NEUTRON LEAKAGE 52 THERMAL ABSORBED BY NON-FUEL ATOMS L th 07 THERMAL f 965 THERMAL

More information

Neutron reproduction. factor ε. k eff = Neutron Life Cycle. x η

Neutron reproduction. factor ε. k eff = Neutron Life Cycle. x η Neutron reproduction factor k eff = 1.000 What is: Migration length? Critical size? How does the geometry affect the reproduction factor? x 0.9 Thermal utilization factor f x 0.9 Resonance escape probability

More information

Reactivity Balance & Reactor Control System

Reactivity Balance & Reactor Control System Reactivity Balance & Reactor Control System K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University Joint Initiative of IITs and IISc Funded by MHRD Page 1 of 6 Table of Contents 1 MULTIPLICATION

More information

Serco Assurance. Resonance Theory and Transport Theory in WIMSD J L Hutton

Serco Assurance. Resonance Theory and Transport Theory in WIMSD J L Hutton Serco Assurance Resonance Theory and Transport Theory in WIMSD J L Hutton 2 March 2004 Outline of Talk Resonance Treatment Outline of problem - pin cell geometry U 238 cross section Simple non-mathematical

More information

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 1. Title: Neutron Life Cycle

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 1. Title: Neutron Life Cycle Lectures on Nuclear Power Safety Lecture No 1 Title: Neutron Life Cycle Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture Infinite Multiplication Factor, k Four Factor Formula

More information

Fundamentals of Nuclear Reactor Physics

Fundamentals of Nuclear Reactor Physics Fundamentals of Nuclear Reactor Physics E. E. Lewis Professor of Mechanical Engineering McCormick School of Engineering and Applied Science Northwestern University AMSTERDAM BOSTON HEIDELBERG LONDON NEW

More information

Nuclear Reactor Physics I Final Exam Solutions

Nuclear Reactor Physics I Final Exam Solutions .11 Nuclear Reactor Physics I Final Exam Solutions Author: Lulu Li Professor: Kord Smith May 5, 01 Prof. Smith wants to stress a couple of concepts that get people confused: Square cylinder means a cylinder

More information

Excerpt from the Proceedings of the COMSOL Users Conference 2007 Grenoble

Excerpt from the Proceedings of the COMSOL Users Conference 2007 Grenoble Excerpt from the Proceedings of the COSOL Users Conference 007 Grenoble Evaluation of the moderator temperature coefficient of reactivity in a PWR V. emoli *,, A. Cammi Politecnico di ilano, Department

More information

A Method For the Burnup Analysis of Power Reactors in Equilibrium Operation Cycles

A Method For the Burnup Analysis of Power Reactors in Equilibrium Operation Cycles Journal of NUCLEAR SCIENCE and TECHNOLOGY, 3[5], p.184~188 (May 1966). A Method For the Burnup Analysis of Power Reactors in Equilibrium Operation Cycles Shoichiro NAKAMURA* Received February 7, 1966 This

More information

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 4. Title: Control Rods and Sub-critical Systems

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 4. Title: Control Rods and Sub-critical Systems Lectures on Nuclear Power Safety Lecture No 4 Title: Control Rods and Sub-critical Systems Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture Control Rods Selection of Control

More information

Control of the fission chain reaction

Control of the fission chain reaction Control of the fission chain reaction Introduction to Nuclear Science Simon Fraser University Spring 2011 NUCS 342 April 8, 2011 NUCS 342 (Lecture 30) April 8, 2011 1 / 29 Outline 1 Fission chain reaction

More information

Lesson 14: Reactivity Variations and Control

Lesson 14: Reactivity Variations and Control Lesson 14: Reactivity Variations and Control Reactivity Variations External, Internal Short-term Variations Reactivity Feedbacks Reactivity Coefficients and Safety Medium-term Variations Xe 135 Poisoning

More information

17 Neutron Life Cycle

17 Neutron Life Cycle 17 Neutron Life Cycle A typical neutron, from birth as a prompt fission neutron to absorption in the fuel, survives for about 0.001 s (the neutron lifetime) in a CANDU. During this short lifetime, it travels

More information

Chain Reactions. Table of Contents. List of Figures

Chain Reactions. Table of Contents. List of Figures Chain Reactions 1 Chain Reactions prepared by Wm. J. Garland, Professor, Department of Engineering Physics, McMaster University, Hamilton, Ontario, Canada More about this document Summary: In the chapter

More information

POWER DENSITY DISTRIBUTION BY GAMMA SCANNING OF FUEL RODS MEASUREMENT TECHNIQUE IN RA-8 CRITICAL FACILITY

POWER DENSITY DISTRIBUTION BY GAMMA SCANNING OF FUEL RODS MEASUREMENT TECHNIQUE IN RA-8 CRITICAL FACILITY POWER DENSITY DISTRIBUTION BY GAMMA SCANNING OF FUEL RODS MEASUREMENT TECHNIQUE IN RA-8 CRITICAL FACILITY Eng. Hergenreder, D.F.; Eng. Gennuso, G.; Eng. Lecot, C.A. ABSTRACT Power density measurements

More information

Reactivity Effect of Fission and Absorption

Reactivity Effect of Fission and Absorption Journal of NUCLEAR SCIENCE and TECHNOLOGY, 1, No. 7, p.246~254 (October, 1964). J. Nucl. Sci. Tech. Space Dependent Reactivity Effect of Fission and Absorption Tohru HAGA* and Iwao KOBAYASHI* Received

More information

DESIGN OF B 4 C BURNABLE PARTICLES MIXED IN LEU FUEL FOR HTRS

DESIGN OF B 4 C BURNABLE PARTICLES MIXED IN LEU FUEL FOR HTRS DESIGN OF B 4 C BURNABLE PARTICLES MIXED IN LEU FUEL FOR HTRS V. Berthou, J.L. Kloosterman, H. Van Dam, T.H.J.J. Van der Hagen. Delft University of Technology Interfaculty Reactor Institute Mekelweg 5,

More information

Gauss s Law. 3.1 Quiz. Conference 3. Physics 102 Conference 3. Physics 102 General Physics II. Monday, February 10th, Problem 3.

Gauss s Law. 3.1 Quiz. Conference 3. Physics 102 Conference 3. Physics 102 General Physics II. Monday, February 10th, Problem 3. Physics 102 Conference 3 Gauss s Law Conference 3 Physics 102 General Physics II Monday, February 10th, 2014 3.1 Quiz Problem 3.1 A spherical shell of radius R has charge Q spread uniformly over its surface.

More information

Reactors and Fuels. Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV

Reactors and Fuels. Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV Reactors and Fuels Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV July 19-21, 2011 This course is partially based on work supported by

More information

The Henryk Niewodniczański INSTITUTE OF NUCLEAR PHYSICS Polish Academy of Sciences ul. Radzikowskiego 152, Kraków, Poland.

The Henryk Niewodniczański INSTITUTE OF NUCLEAR PHYSICS Polish Academy of Sciences ul. Radzikowskiego 152, Kraków, Poland. The Henryk Niewodniczański INSTITUTE OF NUCLEAR PHYSICS Polish Academy of Sciences ul. Radzikowskiego 152, 31-342 Kraków, Poland. www.ifj.edu.pl/reports/23.html Kraków, listopad 23 Report No: 1933/PN Influence

More information

Advanced Heavy Water Reactor. Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA

Advanced Heavy Water Reactor. Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA Advanced Heavy Water Reactor Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA Design objectives of AHWR The Advanced Heavy Water Reactor (AHWR) is a unique reactor designed

More information

Delayed neutrons in nuclear fission chain reaction

Delayed neutrons in nuclear fission chain reaction Delayed neutrons in nuclear fission chain reaction 1 Critical state Temporal flow Loss by leakage Loss by Absorption If the number of neutrons (the number of fission reactions) is practically constant

More information

Power Series. Part 1. J. Gonzalez-Zugasti, University of Massachusetts - Lowell

Power Series. Part 1. J. Gonzalez-Zugasti, University of Massachusetts - Lowell Power Series Part 1 1 Power Series Suppose x is a variable and c k & a are constants. A power series about x = 0 is c k x k A power series about x = a is c k x a k a = center of the power series c k =

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

Lecture 27 Reactor Kinetics-III

Lecture 27 Reactor Kinetics-III Objectives In this lecture you will learn the following In this lecture we will understand some general concepts on control. We will learn about reactivity coefficients and their general nature. Finally,

More information

Subcritical Multiplication and Reactor Startup

Subcritical Multiplication and Reactor Startup 22.05 Reactor Physics - Part Twenty-Five Subcritical Multiplication and Reactor Startup 1. Reference Material See pp. 357-363 of the article, Light Water Reactor Control Systems, in Wiley Encyclopedia

More information

Source Neutron Amplification and "Criticality Safety Margin" of an Energy Amplifier

Source Neutron Amplification and Criticality Safety Margin of an Energy Amplifier united nations educational, scientific and cultural organization the international centre for theoretical physics international atomic energy agency SMR/1326-12 Workshop on Hybrid Nuclear Systems for Energy

More information

USA HTR NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL TESTING REACTOR

USA HTR NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL TESTING REACTOR Proceedings of HTR2008 4 th International Topical Meeting on High Temperature Reactors September 28-October 1, 2008, Washington, D.C, USA HTR2008-58155 NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL

More information

MNFFY 221/SIF 4082 Energy and Environmental Physics. 2002

MNFFY 221/SIF 4082 Energy and Environmental Physics. 2002 MNFFY 221/SIF 4082 Energy and Environmental Physics. 2002 Suggested solution to exam Problem 2 a) Show that the energy received from the sun earth is on average equal to the solar constant S given by 1

More information

III. Chain Reactions and Criticality

III. Chain Reactions and Criticality III. Chain Reactions and Criticality Introduction We know that neutron production and loss rates determine the behavior of a nuclear reactor. In this chapter we introduce some terms that help us describe

More information

PHYSICS AND KINETICS OF TRIGA REACTOR. H. Böck and M. Villa AIAU 27307

PHYSICS AND KINETICS OF TRIGA REACTOR. H. Böck and M. Villa AIAU 27307 PHYSICS AND KINETICS OF TRIGA REACTOR H. Böck and M. Villa AIAU 27307 *prepared for NTEC Overview This training module is written as an introduction to reactor physics for reactor operators. It assumes

More information

REACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN PWRs

REACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN PWRs REACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN s Present address: J.L. Kloosterman Interfaculty Reactor Institute Delft University of Technology Mekelweg 15, NL-2629 JB Delft, the Netherlands Fax: ++31

More information

"Control Rod Calibration"

Control Rod Calibration TECHNICAL UNIVERSITY DRESDEN Institute of Power Engineering Training Reactor Reactor Training Course Experiment "Control Rod Calibration" Instruction for Experiment Control Rod Calibration Content: 1...

More information

3. State each of the four types of inelastic collisions, giving an example of each (zaa type example is acceptable)

3. State each of the four types of inelastic collisions, giving an example of each (zaa type example is acceptable) Nuclear Theory - Course 227 OBJECTIVES to: At the conclusion of this course the trainee will be able 227.00-1 Nuclear Structure 1. Explain and use the ZXA notation. 2. Explain the concept of binding energy.

More information

ENEN/Reactor Theory/ Laboratory Session 1 DETERMINATION OF BASIC STATIC REACTOR PARAMETERS IN THE GRAPHITE PILE AT THE VENUS FACILITY

ENEN/Reactor Theory/ Laboratory Session 1 DETERMINATION OF BASIC STATIC REACTOR PARAMETERS IN THE GRAPHITE PILE AT THE VENUS FACILITY p1 Summary DETERMINATION OF BASIC STATIC REACTOR PARAMETERS IN THE GRAPHITE PILE AT THE VENUS FACILITY P. Baeten (pbaeten@sccen.be) The purpose of this laboratory session is the determination of the basic

More information

On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors

On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors Raquel Ochoa Nuclear Engineering Department UPM CONTENTS: 1. Introduction 2. Comparison with ERANOS 3. Parameters required

More information

Potential & Potential Energy

Potential & Potential Energy Potential & Potential Energy Lecture 10: Electromagnetic Theory Professor D. K. Ghosh, Physics Department, I.I.T., Bombay Electrostatic Boundary Conditions : We had seen that electric field has a discontinuity

More information

Experimental and computational determination of Alpha modes of the Delphi subcritical assembly

Experimental and computational determination of Alpha modes of the Delphi subcritical assembly Delft University of Technology Faculty of Applied Sciences Department of Radiation Radionuclides & Reactors Physics of Nuclear Reactors Experimental and computational determination of Alpha modes of the

More information

Applicability of Point Reactor Kinetic Equations for Subcriticality Monitoring

Applicability of Point Reactor Kinetic Equations for Subcriticality Monitoring Proceedings of Korean Nuclear Society Spring Meeting Cheji, Korea, May 21 Applicability of Point Reactor Kinetic Equations for Subcriticality Monitoring Yoichiro Shimazu, Masashi Tsuji Hokkaido University

More information

NEUTRONIC CALCULATION SYSTEM FOR CANDU CORE BASED ON TRANSPORT METHODS

NEUTRONIC CALCULATION SYSTEM FOR CANDU CORE BASED ON TRANSPORT METHODS Romanian Reports in Physics, Vol. 63, No. 4, P. 948 960, 2011 NEUTRONIC CALCULATION SYSTEM FOR CANDU CORE BASED ON TRANSPORT METHODS V. BALACEANU 1, M. PAVELESCU 2 1 Institute for Nuclear Research, PO

More information

Breeding K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University

Breeding K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University Breeding K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University Joint Initiative of IITs and IISc Funded by MHRD Page 1 of 7 Table of Contents 1 NEED FOR BREEDING... 3 1.1 COMPARISON

More information

CHAPTER 4 Reactor Statics. Table of Contents

CHAPTER 4 Reactor Statics. Table of Contents CHAPTER 4 Reactor Statics Prepared by Dr. Benjamin Rouben, & Consulting, Adjunct Proessor, McMaster University & University o Ontario Institute o Technology (UOIT) and Dr. Eleodor Nichita, Associate Proessor,

More information

Boundary value problems

Boundary value problems 1 Introduction Boundary value problems Lecture 5 We have found that the electric potential is a solution of the partial differential equation; 2 V = ρ/ǫ 0 The above is Poisson s equation where ρ is the

More information

Lecture 13: Electromagnetic Theory Professor D. K. Ghosh, Physics Department, I.I.T., Bombay. Poisson s and Laplace s Equations

Lecture 13: Electromagnetic Theory Professor D. K. Ghosh, Physics Department, I.I.T., Bombay. Poisson s and Laplace s Equations Poisson s and Laplace s Equations Lecture 13: Electromagnetic Theory Professor D. K. Ghosh, Physics Department, I.I.T., Bombay We will spend some time in looking at the mathematical foundations of electrostatics.

More information

PHYS-E0562 Ydinenergiatekniikan jatkokurssi Lecture 4 Diffusion theory

PHYS-E0562 Ydinenergiatekniikan jatkokurssi Lecture 4 Diffusion theory PHYS-E0562 Ydinenergiatekniikan jatkokurssi Lecture 4 Diffusion theory Jaakko Leppänen (Lecturer), Ville Valtavirta (Assistant) Department of Applied Physics Aalto University, School of Science Jaakko.Leppanen@aalto.fi

More information

High performance computing for neutron diffusion and transport equations

High performance computing for neutron diffusion and transport equations High performance computing for neutron diffusion and transport equations Horizon Maths 2012 Fondation Science Mathématiques de Paris A.-M. Baudron, C. Calvin, J. Dubois, E. Jamelot, J.-J. Lautard, O. Mula-Hernandez

More information

MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT

MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT R. KHAN, M. VILLA, H. BÖCK Vienna University of Technology Atominstitute Stadionallee 2, A-1020, Vienna, Austria ABSTRACT The Atominstitute

More information

Nuclear Theory - Course 227

Nuclear Theory - Course 227 Lesson 227.00-2 NEUTRON BALANCE Nuclear Theory - Course 227 DURNG STEADY REACTOR OPERATON We have seen, in the previous lesson, what type of neutrons are produced and how they are produced in a reactor.

More information

CALCULATION OF TEMPERATURE REACTIVITY COEFFICIENTS IN KRITZ-2 CRITICAL EXPERIMENTS USING WIMS ABSTRACT

CALCULATION OF TEMPERATURE REACTIVITY COEFFICIENTS IN KRITZ-2 CRITICAL EXPERIMENTS USING WIMS ABSTRACT CALCULATION OF TEMPERATURE REACTIVITY COEFFICIENTS IN KRITZ-2 CRITICAL EXPERIMENTS USING WIMS D J Powney AEA Technology, Nuclear Science, Winfrith Technology Centre, Dorchester, Dorset DT2 8DH United Kingdom

More information

New methods implemented in TRIPOLI-4. New methods implemented in TRIPOLI-4. J. Eduard Hoogenboom Delft University of Technology

New methods implemented in TRIPOLI-4. New methods implemented in TRIPOLI-4. J. Eduard Hoogenboom Delft University of Technology New methods implemented in TRIPOLI-4 New methods implemented in TRIPOLI-4 J. Eduard Hoogenboom Delft University of Technology on behalf of Cheikh Diop (WP1.1 leader) and all other contributors to WP1.1

More information

THREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS

THREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS THREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS Carsten Beckert 1. Introduction To calculate the neutron transport in a reactor, it is often

More information

Nuclear Physics (13 th lecture)

Nuclear Physics (13 th lecture) uclear Physics ( th lecture) Cross sections of special neutron-induced reactions UCLR FISSIO Mechanism and characteristics of nuclear fission. o The fission process o Mass distribution of the fragments

More information

A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations

A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations S. Nicolas, A. Noguès, L. Manifacier, L. Chabert TechnicAtome, CS 50497, 13593 Aix-en-Provence Cedex

More information

Nuclear Theory - Course 127 EFFECTS OF FUEL BURNUP

Nuclear Theory - Course 127 EFFECTS OF FUEL BURNUP Nuclear Theory - Course 127 EFFECTS OF FUEL BURNUP The effect of fuel burnup wa~ considered, to some extent, in a previous lesson. During fuel burnup, U-235 is used up and plutonium is produced and later

More information

in U. S. Department of Energy Nuclear Criticality Technology and Safety Project 1995 Annual Meeting SanDiego, CA

in U. S. Department of Energy Nuclear Criticality Technology and Safety Project 1995 Annual Meeting SanDiego, CA T. LESSONS LEARNED FROM APPLYING VIM TO FAST REACTOR CRITICAL EXPERIMENTS by R. W. Schaefer, R. D. McKnight and P. J. Collins Argonne National Laboratory P. 0. Box 2528 Idaho Falls, ID 83404-2528 Summary

More information

VI. Chain Reaction. Two basic requirements must be filled in order to produce power in a reactor:

VI. Chain Reaction. Two basic requirements must be filled in order to produce power in a reactor: VI. Chain Reaction VI.1. Basic of Chain Reaction Two basic requirements must be filled in order to produce power in a reactor: The fission rate should be high. This rate must be continuously maintained.

More information

Study of the End Flux Peaking for the CANDU Fuel Bundle Types by Transport Methods

Study of the End Flux Peaking for the CANDU Fuel Bundle Types by Transport Methods International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 Study of the End Flux Peaking for the CANDU Fuel Bundle Types by Transport Methods ABSTRACT Victoria Balaceanu,

More information

Low-Grade Nuclear Materials as Possible Threats to the Nonproliferation Regime. (Report under CRDF Project RX0-1333)

Low-Grade Nuclear Materials as Possible Threats to the Nonproliferation Regime. (Report under CRDF Project RX0-1333) Low-Grade Nuclear Materials as Possible Threats to the Nonproliferation Regime (Report under CRDF Project RX0-1333) 2 Abstract This study addresses a number of issues related to low-grade fissile materials

More information

Estimation of Control Rods Worth for WWR-S Research Reactor Using WIMS-D4 and CITATION Codes

Estimation of Control Rods Worth for WWR-S Research Reactor Using WIMS-D4 and CITATION Codes Estimation of Control Rods Worth for WWR-S Research Reactor Using WIMS-D4 and CITATION Codes M. S. El-Nagdy 1, M. S. El-Koliel 2, D. H. Daher 1,2 )1( Department of Physics, Faculty of Science, Halwan University,

More information

A MONTE CARLO METHOD FOR CALCULATING INITIATION PROBABILITY

A MONTE CARLO METHOD FOR CALCULATING INITIATION PROBABILITY Supercomputing in Nuclear Applications (M&C + SNA 2007) Monterey, California, April 15-19, 2007, on CD-ROM, American Nuclear Society, La Grange Park, IL (2007) A MONTE CARLO METHOD FOR CALCULATING INITIATION

More information

Chem 481 Lecture Material 4/22/09

Chem 481 Lecture Material 4/22/09 Chem 481 Lecture Material 4/22/09 Nuclear Reactors Poisons The neutron population in an operating reactor is controlled by the use of poisons in the form of control rods. A poison is any substance that

More information

Student-level numerical simulation of conditions inside an exploding fission-bomb core

Student-level numerical simulation of conditions inside an exploding fission-bomb core Vol.2, No.3, 139-144 (2010) http://dx.doi.org/10.4236/ns.2010.23023 Natural Science Student-level numerical simulation of conditions inside an exploding fission-bomb Bruce Cameron Reed Department of Physics

More information

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 5. Title: Reactor Kinetics and Reactor Operation

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 5. Title: Reactor Kinetics and Reactor Operation Lectures on Nuclear Power Safety Lecture No 5 Title: Reactor Kinetics and Reactor Operation Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture (1) Reactor Kinetics Reactor

More information

Characterization of a Portable Neutron Coincidence Counter Angela Thornton and W. Charlton Texas A&M University College Station, TX

Characterization of a Portable Neutron Coincidence Counter Angela Thornton and W. Charlton Texas A&M University College Station, TX Characterization of a Portable Neutron Coincidence Counter Angela Thornton and W. Charlton Texas A&M University College Station, TX 77843 Abstract Neutron coincidence counting is a technique widely used

More information

Efficient Energy Conversion of the 14MeV Neutrons in DT Inertial Confinement Fusion. By F. Winterberg University of Nevada, Reno

Efficient Energy Conversion of the 14MeV Neutrons in DT Inertial Confinement Fusion. By F. Winterberg University of Nevada, Reno Efficient Energy Conversion of the 14MeV Neutrons in DT Inertial Confinement Fusion By F. Winterberg University of Nevada, Reno Abstract In DT fusion 80% of the energy released goes into 14MeV neutrons,

More information

JOYO MK-III Performance Test at Low Power and Its Analysis

JOYO MK-III Performance Test at Low Power and Its Analysis PHYSOR 200 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25-29, 200, on CD-ROM, American Nuclear Society, Lagrange Park, IL. (200) JOYO MK-III Performance

More information

AP Physics C. Gauss s Law. Free Response Problems

AP Physics C. Gauss s Law. Free Response Problems AP Physics Gauss s Law Free Response Problems 1. A flat sheet of glass of area 0.4 m 2 is placed in a uniform electric field E = 500 N/. The normal line to the sheet makes an angle θ = 60 ẘith the electric

More information

The collision probability method in 1D part 2

The collision probability method in 1D part 2 The collision probability method in 1D part 2 Alain Hébert alain.hebert@polymtl.ca Institut de génie nucléaire École Polytechnique de Montréal ENE611: Week 9 The collision probability method in 1D part

More information

Effect of WIMSD4 libraries on Bushehr VVER-1000 Core Fuel Burn-up

Effect of WIMSD4 libraries on Bushehr VVER-1000 Core Fuel Burn-up International Conference Nuccllearr Enerrgy fforr New Eurrope 2009 Bled / Slovenia / September 14-17 ABSTRACT Effect of WIMSD4 libraries on Bushehr VVER-1000 Core Fuel Burn-up Ali Pazirandeh and Elham

More information

1 Introduction. Green s function notes 2018

1 Introduction. Green s function notes 2018 Green s function notes 8 Introduction Back in the "formal" notes, we derived the potential in terms of the Green s function. Dirichlet problem: Equation (7) in "formal" notes is Φ () Z ( ) ( ) 3 Z Φ (

More information

Critical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models

Critical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 42, No. 1, p. 101 108 (January 2005) TECHNICAL REPORT Critical Experiment Analyses by CHAPLET-3D Code in Two- and Three-Dimensional Core Models Shinya KOSAKA

More information

Solving Bateman Equation for Xenon Transient Analysis Using Numerical Methods

Solving Bateman Equation for Xenon Transient Analysis Using Numerical Methods Solving Bateman Equation for Xenon Transient Analysis Using Numerical Methods Zechuan Ding Illume Research, 405 Xintianshiji Business Center, 5 Shixia Road, Shenzhen, China Abstract. After a nuclear reactor

More information

PhD Qualifying Exam Nuclear Engineering Program. Part 1 Core Courses

PhD Qualifying Exam Nuclear Engineering Program. Part 1 Core Courses PhD Qualifying Exam Nuclear Engineering Program Part 1 Core Courses 9:00 am 12:00 noon, November 19, 2016 (1) Nuclear Reactor Analysis During the startup of a one-region, homogeneous slab reactor of size

More information

CRITICAL AND SUBCRITICAL EXPERIMENTS USING THE TRAINING NUCLEAR REACTOR OF THE BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS

CRITICAL AND SUBCRITICAL EXPERIMENTS USING THE TRAINING NUCLEAR REACTOR OF THE BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS CRITICAL AND SUBCRITICAL EXPERIMENTS USING THE TRAINING NUCLEAR REACTOR OF THE BUDAPEST UNIVERSITY OF TECHNOLOGY AND ECONOMICS É. M. Zsolnay Department of Nuclear Techniques, Budapest University of Technology

More information

Lecture 18 Neutron Kinetics Equations

Lecture 18 Neutron Kinetics Equations 24.505 Lecture 18 Neutron Kinetics Equations Prof. Dean Wang For a nuclear reactor to operate at a constant power level, the rate of neutron production via fission reactions should be exactly balanced

More information

A Hybrid Deterministic / Stochastic Calculation Model for Transient Analysis

A Hybrid Deterministic / Stochastic Calculation Model for Transient Analysis A Hybrid Deterministic / Stochastic Calculation Model for Transient Analysis A. Aures 1,2, A. Pautz 2, K. Velkov 1, W. Zwermann 1 1 Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh Boltzmannstraße

More information

MURI teleconference 28 May Optical Antimatter. John Pendry and Sebastien Guenneau Imperial College London. 24 May 2004 page 1

MURI teleconference 28 May Optical Antimatter. John Pendry and Sebastien Guenneau Imperial College London. 24 May 2004 page 1 24 May 2004 page 1 MURI teleconference 28 May 2004 Optical Antimatter John Pendry and Sebastien Guenneau Imperial College London 05 March 2004 page 2 A Conventional Lens Contributions of the far field

More information

Nuclear Theory - Course 127 NEUTRON BALANCE AND THE FOUR FACTOR FORMULA

Nuclear Theory - Course 127 NEUTRON BALANCE AND THE FOUR FACTOR FORMULA ' Nuclear Theory - Course 127 NEUTRON BALANCE AND THE FOUR FACTOR FORMULA When a reactor is operating at steady power, the chain reaction is just being maintained. One neutro~ only is available from each

More information

Lecture 10. Central potential

Lecture 10. Central potential Lecture 10 Central potential 89 90 LECTURE 10. CENTRAL POTENTIAL 10.1 Introduction We are now ready to study a generic class of three-dimensional physical systems. They are the systems that have a central

More information

Energy Dependence of Neutron Flux

Energy Dependence of Neutron Flux Energy Dependence of Neutron Flux B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2015 September 1 Contents We start the discussion of the energy

More information

Postprint.

Postprint. http://www.diva-portal.org Postprint This is the accepted version of a paper published in Annals of Nuclear Energy. This paper has been peer-reviewed but does not include the final publisher proof-corrections

More information

Form #221 Page 1 of 7

Form #221 Page 1 of 7 Version Quiz #2 Form #221 Name: A Physics 2212 GH Spring 2016 Recitation Section: Print your name, quiz form number (3 digits at the top of this form), and student number (9 digit Georgia Tech ID number)

More information

Theoretical Task 3 (T-3) : Solutions 1 of 9

Theoretical Task 3 (T-3) : Solutions 1 of 9 Theoretical Task 3 (T-3) : Solutions of 9 The Design of a Nuclear Reactor Uranium occurs in nature as UO with only 0.70% of the uranium atoms being 35 U. Neutron induced fission occurs readily in 35 U

More information

REFLECTOR FEEDBACK COEFFICIENT: NEUTRONIC CONSIDERATIONS IN MTR-TYPE RESEARCH REACTORS ABSTRACT

REFLECTOR FEEDBACK COEFFICIENT: NEUTRONIC CONSIDERATIONS IN MTR-TYPE RESEARCH REACTORS ABSTRACT REFLECTOR FEEDBACK COEFFICIENT: NEUTRONIC CONSIDERATIONS IN MTR-TYPE RESEARCH REACTORS L. MANIFACIER, L. CHABERT, M. BOYARD TechnicAtome, CS 50497, 13593 Aix-en-Provence Cedex 3, France ABSTRACT Having

More information

Fundamental Stellar Parameters. Radiative Transfer. Stellar Atmospheres

Fundamental Stellar Parameters. Radiative Transfer. Stellar Atmospheres Fundamental Stellar Parameters Radiative Transfer Stellar Atmospheres Equations of Stellar Structure Basic Principles Equations of Hydrostatic Equilibrium and Mass Conservation Central Pressure, Virial

More information

Module 6. Neutron Flux Distribution 6.1 MODULE OVERVIEW '!' MODULE OBJECTIVES OVERALL FLUX SHAPE FLUX FLATTENING 6

Module 6. Neutron Flux Distribution 6.1 MODULE OVERVIEW '!' MODULE OBJECTIVES OVERALL FLUX SHAPE FLUX FLATTENING 6 Module 6 Neutron Flux Distribution 6.1 MODULE OVERVIEW '!' 2 6.2 MODULE OBJECTIVES 2 6.3 OVERALL FLUX SHAPE 3 6.4 FLUX FLATTENING 6 6.4.1 The Reflector 7 6.4.2 Bi-

More information

ELECTRO MAGNETIC FIELDS

ELECTRO MAGNETIC FIELDS SET - 1 1. a) State and explain Gauss law in differential form and also list the limitations of Guess law. b) A square sheet defined by -2 x 2m, -2 y 2m lies in the = -2m plane. The charge density on the

More information

Nuclear Theory - Course 227 NEUTRON FLUX DISTRI~UTION

Nuclear Theory - Course 227 NEUTRON FLUX DISTRI~UTION Nuclear Theory - Course 227 NEUTRON FLUX DSTR~UTON. From neutron diffusi'on t-heory it is possible to derive the steady state flux distribution in a reactor. Since the flux is not normally the ~;ame everywhere

More information

INTRODUCTION TO NUCLEAR REACTORS AND NUCLEAR POWER GENERATION. Atsushi TAKEDA & Hisao EDA

INTRODUCTION TO NUCLEAR REACTORS AND NUCLEAR POWER GENERATION. Atsushi TAKEDA & Hisao EDA INTRODUCTION TO NUCLEAR REACTORS AND NUCLEAR POWER GENERATION Atsushi TAKEDA & Hisao EDA 1 CONTENTS The first step toward nuclear power Physics of nuclear fission Sustained chain reaction in nuclear reactor

More information

THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR

THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 ABSTRACT THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR Boris Bergelson, Alexander Gerasimov Institute

More information

Chemical Reaction between Solids x 2 = Kt

Chemical Reaction between Solids x 2 = Kt 2-2.1.2 Chemical Reaction between Solids The simplest system involves the reaction between two solid phases, A and B, to produce a solid solution C, A and B are commonly elements for metallic systems,

More information

Reactivity Coefficients

Reactivity Coefficients Reactivity Coefficients B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2015 September 1 Reactivity Changes In studying kinetics, we have seen

More information