Reactivity Balance & Reactor Control System

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

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

Lecture 20 Reactor Theory-V

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

Delayed neutrons in nuclear fission chain reaction

Design constraints Maximum clad temperature, linear power rating

Chain Reactions. Table of Contents. List of Figures

Nuclear Theory - Course 127 EFFECTS OF FUEL BURNUP

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

Control of the fission chain reaction

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

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

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

Subcritical Multiplication and Reactor Startup

Lecture 27 Reactor Kinetics-III

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

17 Neutron Life Cycle

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

Operational Reactor Safety

Fundamentals of Nuclear Reactor Physics

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

Nuclear Theory - Course 227

Reactor Operation Without Feedback Effects

Lesson 9: Multiplying Media (Reactors)

2. The Steady State and the Diffusion Equation

Nuclear Physics (13 th lecture)

NEUTRON MODERATION. LIST three desirable characteristics of a moderator.

Introduction to Reactivity and Reactor Control

Reactivity Coefficients

III. Chain Reactions and Criticality

Chem 481 Lecture Material 4/22/09

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

X. Assembling the Pieces

Reactivity Coefficients

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

Lecture 28 Reactor Kinetics-IV

Lesson 8: Slowing Down Spectra, p, Fermi Age

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

"Control Rod Calibration"

Chemical Engineering 412

Reactor Kinetics and Operation

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

Elastic scattering. Elastic scattering

Power Changes in a Critical Reactor. The Critical Reactor

XV. Fission Product Poisoning

Lecture 5 Nuclear Reactions

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

Nuclear Theory - Course 227 REACTIVITY EFFECTS DUE TO TEMPERATURE CHANGES

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

Nuclear Reactor Physics I Final Exam Solutions

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

12 Moderator And Moderator System

Quiz, Physics & Chemistry

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

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

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

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

REACTOR PHYSICS ASPECTS OF PLUTONIUM RECYCLING IN PWRs

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

Lesson 14: Reactivity Variations and Control

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

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

VIII. Neutron Moderation and the Six Factors

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

Chemical Engineering 412

Energy Dependence of Neutron Flux

Energy & Sustainability

Neutron Interactions with Matter

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

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

Monte Carlo Methods in Reactor Physics

6 Neutrons and Neutron Interactions

Strain Transformation equations

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

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

Nuclear Theory - Course 227 THERMAL REACTORS (BASIC DESIGN)

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

Mechanical Engineering Introduction to Nuclear Engineering /12

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

MCRT L8: Neutron Transport

Nuclear Energy ECEG-4405

Nuclear Binding Energy

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

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

Lecture 7 Problem Set-2

Lecture 18 Neutron Kinetics Equations

Michaelis Menten Kinetics- Identical Independent Binding Sites

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

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

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

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

Nuclear Energy Learning Outcomes

Nuclear Energy Learning Outcomes. Nuclear Fission. Chain Reaction

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

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

MNFFY 221/SIF 4082 Energy and Environmental Physics. 2002

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

NUCLEI. Atomic mass unit

Moderator & Moderator System

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

Transcription:

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 FACTOR... 3 2 FIVE- FACTOR AND FOUR- FACTOR FORMULAE... 4 2.1 REACTIVITY... 4 2.1.1 Reactivity coefficients... 5 3 INTRODUCTION TO REACTOR CONTROL SYSTEM... 6 4 REFERENCES/ADDITIONAL READING... 6 Joint Initiative of IITs and IISc Funded by MHRD Page 2 of 6

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

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 1.02. 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

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 = 0.0065; 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 0 2.1.1 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

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. https://canteach.candu.org/content%20library/20050317.pdf Joint Initiative of IITs and IISc Funded by MHRD Page 6 of 6