Reactivity Balance & Reactor Control System

Size: px
Start display at page:

Download "Reactivity Balance & Reactor Control System"

Transcription

1 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

2 Table of Contents 1 MULTIPLICATION FACTOR FIVE- FACTOR AND FOUR- FACTOR FORMULAE REACTIVITY Reactivity coefficients INTRODUCTION TO REACTOR CONTROL SYSTEM REFERENCES/ADDITIONAL READING... 6 Joint Initiative of IITs and IISc Funded by MHRD Page 2 of 6

3 In this lecture, we shall discuss four-factor formula for multiplication factor along with its utility in determining reactivity in a reactor. The later part of this lecture will include introduction to reactor control system. At the end of this lecture, the learners will be able to (i) understand the four-factor formula for multiplication factor (ii) list the factors influencing the multiplication factor (iii) relate multiplication factor with reactivity (iv) understand the basic functions of a control system 1 Multiplication factor In a nuclear reactor, self-sustaining chain reaction takes place. In other words, once the fission is initiated with neutrons in a critical mass of nuclear fuel, the neutrons obtained after every fission event is used to sustain the reaction, without the use of external source of neutrons. The neutrons produced per fission event must be large enough to sustain the chain reaction, despite the loss of neutrons due to leakage and by absorption in non-fissile materials. A criticality factor or effective multiplication factor (k) is defined to denote the relative number of neutrons produced in successive fission events. In effect, k is the ratio of number of neutrons produced by fission in one generation to the number of neutrons produced by fission in the preceding generation. If a system is critical, the multiplication factor is 1. Supercritical systems have multiplication factors greater than 1, while subcritical systems have multiplication factors lesser than 1. The important parameters to note in this context are: (i) average number of neutrons produced per fission event (ν) (ii) average number of fission neutrons produced per thermal neutron absorbed in the fuel (η) The above two factors are different, but are related. Let us take that during one fission event ν number of neutrons are produced. When these neutrons are absorbed in the fuel, some of them may induce fission while some of them may not. This depends on the ratio of fission to absorption cross sections. For a pure fissile material, the number of fissions produced per neutron absorbed is related to the average number of neutrons produced per fission event as follows:!! =!!!! (1) Joint Initiative of IITs and IISc Funded by MHRD Page 3 of 6

4 2 Five-factor and Four-factor formulae Apart from η, there are other factors that influence k. For instance, all the neutrons released during a fission event are fast neutrons. There are slowed down by elastic collision with moderator before they induce fission. A fraction of neutrons released that is thermalized can induce fission while the other fraction is captured. This fraction of neutrons released and thermalized is p. This fraction p is called resonance escape probability. The word escape is used as these neutrons escape being captured by fertile material like U-238 and undergo thermalization. Though the fission cross section of U-235 is low in the fast spectrum, the fission cross section is still finite. A part of neutrons that are not thermalized may induce fast fission. The contribution from fast fission is taken as a multiplication factor (ε). The value of ε =1 implies that there is no contribution due to fast fission. Typically the value of ε is taken as Neutrons can be lost, if the reactor core is too small. P L is used to denote the neutron loss from core. The maximum value of P L is 1, when the core is large enough to prevent neutron leakage. The effective multiplication factor, k can be related to all the five factors (η, p, f, P L, ε) as k= pηfp L ε (2) Equation (2) is called five-factor formula. If diameter of the core is large enough to prevent any neutron leakage, P L =1 and hence Eq. (2) becomes k inf = pηfε (3) Equation (3) is called four-factor formula. 2.1 Reactivity Recall the discussion that we had at the beginning of the module with respect to effective multiplication factor. The state of a reactor with respect to its criticality can be judged from the value of effective multiplication factor. To maintain a constant power, k must be equal to 1. Value of k lesser than one results in reduction of power, while k>1 lead to power excursions. Hence the deviation of k from one is a significant factor. Reactivity (ρ) is defined as the ratio of deviation of k from 1 to the value of k. Joint Initiative of IITs and IISc Funded by MHRD Page 4 of 6

5 ρ =!!!! (4) The reactivity (ρ) is expressed in dollars ($). Mean neutron lifetime (l): It is the average time between the emission of a fission neutron and its absorption. The mean neutron lifetime (l) is the average of lifetime of prompt neutrons (l p ) and that of delayed neutrons (l d ). If β is the fraction of delayed neutrons then, l=(1-β)l p +βl d (5) Typically, β = ; l p is of the order of 10-5 s; l d is 12.7 s Reactor period (T): It is obtained from mean neutron lifetime (l) and multiplication factor (k) as follows: If (k-1)< β; T=βl d /(k-1) (6) If (k-1)>β; T=l/(k-1) (7) Both prompt and delayed neutrons contribute to criticality of a reactor. If a reactor is critical by prompt neutrons alone, it is called prompt critical. With the arrival of delayed neutrons, the reactor is likely to become supercritical. The following can be used distinguish different scenario of criticality: ρ = 0; critical or delayed critical 0< ρ < β: supercritical ρ < β; prompt critical ρ >= β; super prompt critical. Hence for the safe and steady-state operation, ρ must be equal to Reactivity coefficients The reactivity in a system may be influenced by temperature, power, void fraction etc. depending on the reactor configuration and other parameters. The influence of these factors on reactivity is normally expressed in terms of coefficients as defined below: Temperature coefficient of reactivity = α = ρ/δt (8) Joint Initiative of IITs and IISc Funded by MHRD Page 5 of 6

6 If α is negative, it indicates that an increase in temperature will reduce reactivity (ρ) and multiplication factor (k). The reverse holds good if α is positive. Power coefficient of reactivity = a = ρ/δp (9) If a is negative, it indicates that an increase in power will reduce reactivity (ρ) and multiplication factor (k). The reverse holds good if a is positive. 3 Introduction to Reactor control system As discussed earlier in the lecture, the multiplication factor and hence the reactivity are functions of temperature, concentration of poisons, etc. For a reactor to operate at constant power, a system must be available to correct for changes in reactivity. Also, provisions must be available to modulate reactor power as required. The reactor control system with the following functions takes care of these requirements: (i) (ii) (iii) To maintain the multiplication factor at 1 (i.e. k =1) and dk = 0 during steady state operation. Any changes to dk during the normal course of operation must be adjusted by the system to maintain k at 1. When there is a requirement for increase in power, the control system must allow dk to attain positive value. Similarly, during the requirement of lower power, the system must allow dk to attain negative value. During shutdown, the reactor control system must decrease k by appreciable amount to allow a large negative value for dk to enable rapid shutdown. The above functions may be categorized as regulation (i & ii) and protection functions (iii). 4 References/Additional Reading 1. Nuclear Energy: An Introduction to the Concepts, Systems, and Applications of Nuclear Processes, 5/e, R.L. Murray, Butterworth Heinemann, 2000 (Chapter 19). 2. David Bodansky, Nuclear Energy: Principles, Practices, and Prospects, 2/e, Springer-Verlag, USA, 2004 (Chapter 7) 3. Joint Initiative of IITs and IISc Funded by MHRD Page 6 of 6

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

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

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

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

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

Design constraints Maximum clad temperature, linear power rating

Design constraints Maximum clad temperature, linear power rating Design constraints Maximum clad temperature, linear power rating K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University Joint Initiative of IITs and IISc Funded by MHRD Page 1 of 7

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

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

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

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

(1) The time t required for N generations to elapse is merely:

(1) The time t required for N generations to elapse is merely: 19 Changes In Reactor Power With Time The two preceding modules discussed how reactivity changes increase or decrease neutron flux and hence, change the thermal power output from the fuel. We saw how the

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

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

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

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

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

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

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

Operational Reactor Safety

Operational Reactor Safety Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Lecture 3 Reactor Kinetics and Control Page 1 Topics to Be Covered Time Dependent Diffusion Equation Prompt

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

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

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

Reactor Operation Without Feedback Effects

Reactor Operation Without Feedback Effects 22.05 Reactor Physics - Part Twenty-Six Reactor Operation Without Feedback Effects 1. Reference Material: See pp. 363-368 of the article, Light Water Reactor Control Systems, in Wiley Encyclopedia of Electrical

More information

Lesson 9: Multiplying Media (Reactors)

Lesson 9: Multiplying Media (Reactors) 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,

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

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

NEUTRON MODERATION. LIST three desirable characteristics of a moderator.

NEUTRON MODERATION. LIST three desirable characteristics of a moderator. Reactor Theory (eutron Characteristics) DOE-HDBK-1019/1-93 EUTRO MODERATIO EUTRO MODERATIO In thermal reactors, the neutrons that cause fission are at a much lower energy than the energy level at which

More information

Introduction to Reactivity and Reactor Control

Introduction to Reactivity and Reactor Control Introduction to Reactivity and Reactor Control Larry Foulke Adjunct Professor Director of Nuclear Education Outreach University of Pittsburgh IAEA Workshop on Desktop Simulation October 2011 Learning Objectives

More information

Reactivity Coefficients

Reactivity Coefficients Revision 1 December 2014 Reactivity Coefficients Student Guide GENERAL DISTRIBUTION GENERAL DISTRIBUTION: Copyright 2014 by the National Academy for Nuclear Training. Not for sale or for commercial use.

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

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

The moderator temperature coefficient MTC is defined as the change in reactivity per degree change in moderator temperature.

The moderator temperature coefficient MTC is defined as the change in reactivity per degree change in moderator temperature. Moderator Temperature Coefficient MTC 1 Moderator Temperature Coefficient The moderator temperature coefficient MTC is defined as the change in reactivity per degree change in moderator temperature. α

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

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

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

Lecture 28 Reactor Kinetics-IV

Lecture 28 Reactor Kinetics-IV Objectives In this lecture you will learn the following In this lecture we will understand the transient build up of Xenon. This can lead to dead time in reactors. Xenon also induces power oscillations

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

CANDU Safety #3 - Nuclear Safety Characteristics Dr. V.G. Snell Director Safety & Licensing

CANDU Safety #3 - Nuclear Safety Characteristics Dr. V.G. Snell Director Safety & Licensing CANDU Safety #3 - Nuclear Safety Characteristics Dr. V.G. Snell Director Safety & Licensing 24/05/01 CANDU Safety - #3 - Nuclear Safety Characteristics.ppt Rev. 0 vgs 1 What Makes A Safe Nuclear Design?

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

Chemical Engineering 412

Chemical Engineering 412 Chemical Engineering 412 Introductory Nuclear Engineering Lecture 18 Nuclear Reactor Theory IV Reactivity Insertions 1 Spiritual Thought 2 Mosiah 2:33 33 For behold, there is a wo pronounced upon him who

More information

Reactor Kinetics and Operation

Reactor Kinetics and Operation Reactor Kinetics and Operation Course No: N03-002 Credit: 3 PDH Gilbert Gedeon, P.E. Continuing Education and Development, Inc. 9 Greyridge Farm Court Stony Point, NY 0980 P: (877) 322-5800 F: (877) 322-4774

More information

Nuclear Physics 2. D. atomic energy levels. (1) D. scattered back along the original direction. (1)

Nuclear Physics 2. D. atomic energy levels. (1) D. scattered back along the original direction. (1) Name: Date: Nuclear Physics 2. Which of the following gives the correct number of protons and number of neutrons in the nucleus of B? 5 Number of protons Number of neutrons A. 5 6 B. 5 C. 6 5 D. 5 2. The

More information

Elastic scattering. Elastic scattering

Elastic scattering. Elastic scattering Elastic scattering Now we have worked out how much energy is lost when a neutron is scattered through an angle, θ We would like to know how much energy, on average, is lost per collision In order to do

More information

Power Changes in a Critical Reactor. The Critical Reactor

Power Changes in a Critical Reactor. The Critical Reactor Chapter 8 Power Changes in a Critical Reactor n For very small reactivity increases n For small reactivity increases n For large reactivity increases/decreases The Critical Reactor < k = hfpel f L t =

More information

XV. Fission Product Poisoning

XV. Fission Product Poisoning XV. Fission Product Poisoning XV.1. Xe 135 Buil-Up As we already know, temperature changes bring short-term effects. That is to say, once a power change is produced it is rapidly manifested as a change

More information

Lecture 5 Nuclear Reactions

Lecture 5 Nuclear Reactions Objectives In this lecture you will learn the following We shall understand the concept of kinetic energy from the perspective of particle physics. We shall conclude that for all practical purposes, mass

More information

The discovery of nuclear reactions need not bring about the destruction of mankind any more than the discovery of matches - Albert Einstein

The discovery of nuclear reactions need not bring about the destruction of mankind any more than the discovery of matches - Albert Einstein The world has achieved brilliance without wisdom, power without conscience. Ours is a world of nuclear giants and ethical infants. - Omar Bradley (US general) The discovery of nuclear reactions need not

More information

Nuclear Theory - Course 227 REACTIVITY EFFECTS DUE TO TEMPERATURE CHANGES

Nuclear Theory - Course 227 REACTIVITY EFFECTS DUE TO TEMPERATURE CHANGES Nuclear Theory - Course 227 REACTIVITY EFFECTS DUE TO TEMPERATURE CHANGES In the lesson on reactor kinetics we ignored any variations ln reactivity due to changes in power. As we saw in the previous lesson

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

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

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

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

Quiz, Physics & Chemistry

Quiz, Physics & Chemistry Eight Sessions 1. Pressurized Water Reactor 2. Quiz, Thermodynamics & HTFF 3. Quiz, Physics & Chemistry 4. Exam #1, Electrical Concepts & Systems 5. Quiz, Materials Science 6. Quiz, Strength of Materials

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

Chapter 7 & 8 Control Rods Fission Product Poisons. Ryan Schow

Chapter 7 & 8 Control Rods Fission Product Poisons. Ryan Schow Chapter 7 & 8 Control Rods Fission Product Poisons Ryan Schow Ch. 7 OBJECTIVES 1. Define rod shadow and describe its causes and effects. 2. Sketch typical differential and integral rod worth curves and

More information

1. What is the phenomenon that best explains why greenhouse gases absorb infrared radiation? D. Diffraction (Total 1 mark)

1. What is the phenomenon that best explains why greenhouse gases absorb infrared radiation? D. Diffraction (Total 1 mark) 1. What is the phenomenon that best explains why greenhouse gases absorb infrared radiation? A. Resonance B. Interference C. Refraction D. Diffraction 2. In which of the following places will the albedo

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

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

Indian Institute of Technology Madras Present NPTEL NATIONAL PROGRAMME ON TECHNOLOGY ENHANCED LEARNING

Indian Institute of Technology Madras Present NPTEL NATIONAL PROGRAMME ON TECHNOLOGY ENHANCED LEARNING Indian Institute of Technology Madras Present NPTEL NATIONAL PROGRAMME ON TECHNOLOGY ENHANCED LEARNING NUCLEAR REACTOR AND SAFETY AN INTRODUCTORY COURSE Module 02 Lecture 02 Basic Physics of Nuclear Fission

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

Nuclear Theory - Course 227. In the previous lesson the neutron multiplication factor (k) was defined as:.

Nuclear Theory - Course 227. In the previous lesson the neutron multiplication factor (k) was defined as:. Nuclear Theory - Course 227 NEU'l'RO~ MULTIPLICAT!ON:..FACTOR AND REACI'IVITY In the previous lesson the neutron multiplication factor (k) was defined as:. k = no. of neutrons in one generation no. of

More information

Nuclear Reactions A Z. Radioactivity, Spontaneous Decay: Nuclear Reaction, Induced Process: x + X Y + y + Q Q > 0. Exothermic Endothermic

Nuclear Reactions A Z. Radioactivity, Spontaneous Decay: Nuclear Reaction, Induced Process: x + X Y + y + Q Q > 0. Exothermic Endothermic Radioactivity, Spontaneous Decay: Nuclear Reactions A Z 4 P D+ He + Q A 4 Z 2 Q > 0 Nuclear Reaction, Induced Process: x + X Y + y + Q Q = ( m + m m m ) c 2 x X Y y Q > 0 Q < 0 Exothermic Endothermic 2

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

20.1 Xenon Production Xe-135 is produced directly in only 0.3% of all U-235 fissions. The following example is typical:

20.1 Xenon Production Xe-135 is produced directly in only 0.3% of all U-235 fissions. The following example is typical: 20 Xenon: A Fission Product Poison Many fission products absorb neutrons. Most absorption cross-sections are small and are not important in short-term operation. Xenon- has a cross-section of approximately

More information

Chemical Engineering 412

Chemical Engineering 412 Chemical Engineering 412 Introductory Nuclear Engineering Exam 1 Review 1 Chapter 1 - Fundamentals 2 Nuclear units Elementary particles/particle physics Isotopic nomenclature Atomic weight/number density

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

Energy & Sustainability

Energy & Sustainability Energy & Sustainability Lecture 20: Nuclear Power April 9, 2009 Radioactive Decay Each radioactive isotope has a characteristic lifetime and decays pathway Each isotope has a given probability of decay

More information

Neutron Interactions with Matter

Neutron Interactions with Matter Radioactivity - Radionuclides - Radiation 8 th Multi-Media Training Course with Nuclides.net (Institute Josžef Stefan, Ljubljana, 13th - 15th September 2006) Thursday, 14 th September 2006 Neutron Interactions

More information

Shutdown Margin. Xenon-Free Xenon removes neutrons from the life-cycle. So, xenonfree is the most reactive condition.

Shutdown Margin. Xenon-Free Xenon removes neutrons from the life-cycle. So, xenonfree is the most reactive condition. 22.05 Reactor Physics - Part Thirty-One Shutdown Margin 1. Shutdown Margin: Shutdown margin (abbreviated here as SDM) is defined as the amount of reactivity by which a reactor is subcritical from a given

More information

turbine (a) (i) Which part of the power station provides thermal (heat) energy from a chain reaction?

turbine (a) (i) Which part of the power station provides thermal (heat) energy from a chain reaction? Nuclear fission and radiation 1 The diagram shows parts of a nuclear power station. control rods boiler steam generator electricity out turbine condenser nuclear reactor (a) (i) Which part of the power

More information

Monte Carlo Methods in Reactor Physics

Monte Carlo Methods in Reactor Physics UNIVERSITY OF LJUBLJANA Faculty of Mathematics and Physics Department of Physics Seminar on Monte Carlo Methods in Reactor Physics Author: Andrej Kavčič Mentor: prof. dr. Matjaž Ravnik Ljubljana, January

More information

6 Neutrons and Neutron Interactions

6 Neutrons and Neutron Interactions 6 Neutrons and Neutron Interactions A nuclear reactor will not operate without neutrons. Neutrons induce the fission reaction, which produces the heat in CANDU reactors, and fission creates more neutrons.

More information

Strain Transformation equations

Strain Transformation equations Strain Transformation equations R. Chandramouli Associate Dean-Research SASTRA University, Thanjavur-613 401 Joint Initiative of IITs and IISc Funded by MHRD Page 1 of 8 Table of Contents 1. Stress transformation

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

SHAWNEE ENVIRONMENTAL SERVICES, INC Identify the definitions of the following terms: a. Nucleon b. Nuclide c. Isotope

SHAWNEE ENVIRONMENTAL SERVICES, INC Identify the definitions of the following terms: a. Nucleon b. Nuclide c. Isotope Course Title: Radiological Control Technician Module Title: uclear Physics Module umber: 1.04 Objectives: 1.04.01 Identify the definitions of the following terms: a. ucleon b. uclide c. Isotope 1.04.02

More information

Nuclear Theory - Course 227 THERMAL REACTORS (BASIC DESIGN)

Nuclear Theory - Course 227 THERMAL REACTORS (BASIC DESIGN) Nuclear Theory - Course 227 THERMAL REACTORS (BASC DESGN) When a U-235 nucleus fissions an average of 2.5 neutrons are released in addition to the energy. This suggests that these neutrons could be used

More information

i. Explain how heat is produced by nuclear flssion Describe what is meant by sub-critical, critical, and supercritical

i. Explain how heat is produced by nuclear flssion Describe what is meant by sub-critical, critical, and supercritical Introduction to CANDU Processes Module 2 - The Reactor Side of the Station ENABLING OBJECTIVES: 2.i 2.2 2.3 2.4 Explain how heat is produced by nuclear flssion. Describe what is meant by sub-critical,

More information

Mechanical Engineering Introduction to Nuclear Engineering /12

Mechanical Engineering Introduction to Nuclear Engineering /12 Mechanical Engineering Objectives In this lecture you will learn the following In this lecture the population and energy scenario in India are reviewed. The imminent rapid growth of nuclear power is brought

More information

N U C L : R E A C T O R O P E R A T I O N A N D R E G U L A T O R Y P O L I C Y, I

N U C L : R E A C T O R O P E R A T I O N A N D R E G U L A T O R Y P O L I C Y, I N U C L 6 0 6 0 : R E A C T O R O P E R A T I O N A N D R E G U L A T O R Y P O L I C Y, I FALL 2013 INSTRUCTORS: Gregory Moffitt & Ryan Schow LECTURES: MONDAY & WEDNESDAY 11:50 AM 1:10 PM MEB 1206 OFFICE

More information

MCRT L8: Neutron Transport

MCRT L8: Neutron Transport MCRT L8: Neutron Transport Recap fission, absorption, scattering, cross sections Fission products and secondary neutrons Slow and fast neutrons Energy spectrum of fission neutrons Nuclear reactor safety

More information

Nuclear Energy ECEG-4405

Nuclear Energy ECEG-4405 Nuclear Energy ECEG-4405 Today s Discussion Technical History and Developments Atom Nuclear Energy concepts and Terms Features Fission Critical Mass Uranium Fission Nuclear Fusion and Fission Fusion Fission

More information

Nuclear Binding Energy

Nuclear Binding Energy Nuclear Binding Energy...increases almost linearly with A; average B/A about 8 MeV per nucleon nuclei most tightly bound around A=60 below A=60, we can release energy by nuclear fusion above A=60, we can

More information

Elements, atoms and more. Contents. Atoms. Binding energy per nucleon. Nuclear Reactors. Atom: cloud of electrons around a nucleus

Elements, atoms and more. Contents. Atoms. Binding energy per nucleon. Nuclear Reactors. Atom: cloud of electrons around a nucleus Delft University of Technology Nuclear Reactors Jan Leen Kloosterman, Reactor Institute Delft, TU-Delft 8-6-0 Challenge the future Contents Elements, atoms and more Introductory physics Reactor physics

More information

Nuclear Reactions. This is an example of nuclear reaction. Now consider a chemical reaction

Nuclear Reactions. This is an example of nuclear reaction. Now consider a chemical reaction Nuclear Reactions. Introduction REDs are important while yellow is less. Nuclear reactions are the transformations that occur when two nuclei collide. The first such reaction was observed by Rutherford

More information

Lecture 7 Problem Set-2

Lecture 7 Problem Set-2 Objectives In this lecture you will learn the following In this lecture we shall practice solving problems. We will solve 5 out of 10 problems in Assignment-2. Background Information Mole Molecular weight

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

Michaelis Menten Kinetics- Identical Independent Binding Sites

Michaelis Menten Kinetics- Identical Independent Binding Sites Michaelis Menten Kinetics- Identical Independent Binding Sites Dr. M. Vijayalakshmi School of Chemical and Biotechnology SASTRA University Joint Initiative of IITs and IISc Funded by MHRD Page 1 of 8 Table

More information

Step 2: Calculate the total amount of U-238 present at time=0. Step 4: Calculate the rate constant for the decay process.

Step 2: Calculate the total amount of U-238 present at time=0. Step 4: Calculate the rate constant for the decay process. LP#9. A meteor contains 0.556 g of Pb-206 to every 1.00g U-238. Determine the age of the meteor. Step 1: Calculate the moles of each nuclide present. 0.566g Pb-206 x 1.00g U-238 x Step 2: Calculate the

More information

Write down the nuclear equation that represents the decay of neptunium 239 into plutonium 239.

Write down the nuclear equation that represents the decay of neptunium 239 into plutonium 239. Q1.A rod made from uranium 238 ( U) is placed in the core of a nuclear reactor where it absorbs free neutrons. When a nucleus of uranium 238 absorbs a neutron it becomes unstable and decays to neptunium

More information

Chemistry 132 NT. Nuclear Chemistry. Review. You can t escape death and taxes. But, at least, death doesn t get worse. Will Rogers

Chemistry 132 NT. Nuclear Chemistry. Review. You can t escape death and taxes. But, at least, death doesn t get worse. Will Rogers Chemistry 3 NT You can t escape death and taxes. But, at least, death doesn t get worse. Will Rogers Chem 3 NT Nuclear Chemistry Module 3 Energy and Nuclear Reactions The core of a nuclear reactor used

More information

Lecture 14, 8/9/2017. Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion

Lecture 14, 8/9/2017. Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion Lecture 14, 8/9/2017 Nuclear Reactions and the Transmutation of Elements Nuclear Fission; Nuclear Reactors Nuclear Fusion Nuclear Reactions and the Transmutation of Elements A nuclear reaction takes place

More information

Nuclear Energy Learning Outcomes

Nuclear Energy Learning Outcomes 1 Nuclear Energy Learning Outcomes Describe the principles underlying fission and fusion. Interpret nuclear reactions. Discuss nuclear weapons. Describe the structure and operation of a nuclear reactor.

More information

Nuclear Energy Learning Outcomes. Nuclear Fission. Chain Reaction

Nuclear Energy Learning Outcomes. Nuclear Fission. Chain Reaction by fastfission public domain by fastfission public domain 1 Nuclear Energy Learning Outcomes Describe the principles underlying fission and fusion. Interpret nuclear reactions. Discuss nuclear weapons.

More information

Sustainable Power Generation Applied Heat and Power Technology. Equations, diagrams and tables

Sustainable Power Generation Applied Heat and Power Technology. Equations, diagrams and tables Sustainable Power Generation Applied Heat and Power Technology Equations, diagrams and tables 1 STEAM CYCLE Enthalpy of liquid water h = c p,liquid (T T ref ) T ref = 273 K (normal conditions). The specific

More information

Lamarsh, "Introduction to Nuclear Reactor Theory", Addison Wesley (1972), Ch. 12 & 13

Lamarsh, Introduction to Nuclear Reactor Theory, Addison Wesley (1972), Ch. 12 & 13 NEEP 428 REACTOR PULSING Page 1 April 2003 References: Lamarsh, "Introduction to Nuclear Reactor Theory", Addison Wesley (1972), Ch. 12 & 13 Notation: Lamarsh (2), "Introduction to Nuclear Engineering",(1975),

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

Xenon Effects. B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec.

Xenon Effects. B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. enon Effects B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2015 September 1 Contents We study the importance of e-135 in the operation of

More information

NUCLEI. Atomic mass unit

NUCLEI. Atomic mass unit 13 NUCLEI Atomic mass unit It is a unit used to express the mass of atoms and particles inside it. One atomic mass unit is the mass of atom. 1u = 1.660539 10. Chadwick discovered neutron. The sum of number

More information

Moderator & Moderator System

Moderator & Moderator System NPTL Chemcal ngneerng Nuclear Reactor Technology Moderator & Moderator System K.S. Rajan Professor, School of Chemcal & Botechnology SASTRA Unversty Jont Intatve of IITs and IISc Funded by MHRD Page of

More information

GCSE 247/02 SCIENCE PHYSICS HIGHER TIER PHYSICS 3. A.M. FRIDAY, 27 May minutes. Candidate Name. Candidate Number.

GCSE 247/02 SCIENCE PHYSICS HIGHER TIER PHYSICS 3. A.M. FRIDAY, 27 May minutes. Candidate Name. Candidate Number. Candidate Name Centre Number Candidate Number GCSE 247/2 SCIENCE PHYSICS HIGHER TIER PHYSICS 3 A.M. FRIDAY, 27 May 211 45 minutes Question 1. For s use Maximum Mark 6 Mark awarded 2. 3. 4. 5. 6. 7. 4 9

More information