Chemical Engineering 412

Size: px
Start display at page:

Download "Chemical Engineering 412"

Transcription

1 Chemical Engineering 412 Introductory Nuclear Engineering Lecture 18 Nuclear Reactor Theory IV Reactivity Insertions 1

2 Spiritual Thought 2 Mosiah 2:33 33 For behold, there is a wo pronounced upon him who listeth to obey that spirit; for if he listeth to obey him, and remaineth and dieth in his sins, the same drinketh damnation to his own soul; for he receiveth for his wages an everlasting punishment, having transgressed the law of God contrary to his own knowledge.

3 Reactivity and Δk ρ = k ( $ ) keff k eff ρ = β 1 = k( $ ) = worth δk k eff ρ = reactivity δk = delta k β = delayed neutron kk oo = fraction ll ββ + ii=1 GG aa ii λ ii + ωω Inhour equation

4 φ T φ T T = = = ρ = A 1 1+ ωl Reactivity Equation Solutions 1 1 dominant term as t 1 ω exp exp ωl p t T p ( ω t ) + A exp( ω t ) ω + 1+ ωl 2 2 approaches 0 rapdily p 6 i = 1 βi ω + λ i General solution for single group of delayed neutrons Definition of reactor or stable period General solution for single group of delayed neutrons Reactivity equation for six group model graphical solution on next page

5 Reactivity Equation Solutions TT = ll kk eeeeee 1 = ll δδδδ = ββββ δδδδ = Reactor period - The time required for a neutron population to change by a factor of e kk eeeeee = 1 + δδδδ = 1 + ββββ TT ττ =Lifetime of delayed neutrons ~12.8s (U235) TT = ββββ δδδδ = ββββ kk eeeeee 1 = ββββ kk eeeeee ρρ = ττ kk eeeeee ρρ($) ττ ρρ $ ϕ(tt) = eeeeee tt TT Remember, Flux is proportional to power. CC PP(tt) = eeeeee tt TT TT = eeeeee PP(tt) CC PP(0) CC TT = eeeeee PP(tt) PP(0)

6 1-level Model Parameters ββ TT1 2,dd(ss) ττ dd (ss) 232 Th U U U Pu Pu Am Am Cm Source: Laboratoire de Physique Subatomique et de Cosmologie

7 Exploration 1 7 What if we add -$0.1 to AP1000 core? P.i ( i s) 3 P( j s) 2 P.f ( k s) i, j, k t.e

8 Exploration 2 8 What if we add $0.1 to AP1000 core? P.i ( i s) P( j s) 10 P.f ( k s) i, j, k t.e

9 Exploration 3 9 What if we add $0.1 to AP1000 core, then after 10 seconds we add -$0.1? P.i ( i s) 3 P( j s) 2 P.f ( k s) i, j, k t.e

10 Reality 10

11 Kinetics 11 This is how reactor power is controlled Control rods add/subtract worth The circumstances we ve seen so far are not a real, however. Why? Often a balancing influence is experienced Feedback Mechanisms!

12 Isotopic Feedbacks (slow) Fuel Burnup (slow) Decrease in reactivity Fuel breeding (slow) Increase in reactivity Fission product poisons (moderate hours) 135 Xe and 149 Sm Decrease reactivity until decay away Burnable Poisons (slow) Decrease reactivity until transmuted away

13 Temperature Feedbacks (fast) Atomic concentration changes Moderator coolant density Void coefficient fuel expansion Neutron energy distribution changes harden spectrum with increased T TRIGA reactor is extreme example Resonance interaction changes Doppler dominant feedback Burnable Poisons Geometry changes

14 Feedback Effects 14 What if we add $0.1 to AP1000 core with void feedbacks included? P.i ( i) P( j) 3 P.f ( k) i, j, k t.f

15 Exotic Reactors Prompt critical (supercritical) behavior refers to reactors that are critical based on prompt neutrons only and hence have very short periods. Reactors can be designed with inherent shutdown characteristics when they become supercritical. General Atomics TRIGA reactor is an example. Such reactors can produce short but intense pulses of neutrons (see chart at left).

16 Ramifications For positive reactivity (increases in power), which necessarily must be small, prompt neutron jump is negligible, (flux essentially unchanged in the short term) For negative reactivity (decreases in power) can be arbitrarily large prompt neutron change can be very large Up to 96% in the case of a scram over about 80 seconds. Fission product decay accounts for up to 6% of total power (for an equilibrium reactor) not affected by the reactivity change cannot reduce by more than about 93% the power output

17 Cluster Control Rods

18 Cruciform Control Rods

19 α T d = ρ = dt d dt Temperature Dependence k 1 = k 1 k dk dt 2 1 k dk dt α T = temperature reactivity feedback coefficient If α T > 0, Unstable increases and decreases in temperature run away to meltdown or shutdown without operator response. If α T < 0, Stable Increases and decreases in temperature self regulate and the reactor stabilizes. reit-wigner describes absorption profile at 0 but Doppler effect broadens peaks, with Different α s for fuel/moderator ittle change in area, at higher temperatures. Different timescales 2 λ Γ Γ Fuel is most rapid r g n γ σ γ ( E) = 2 α 4π prompt 2 Γ ( E Er ) + NRC requires negative α 4 prompt values for licenses

20 Xenon (Iodine, Tellurium) Xenon-135 has a high absorption cross section (2.65x10 6 b in thermal region) and is the most significant absorbing poison. 135 Te β 11sec Fission d X dt 135 = I 6.7 hr Fission λ I I = λ I I β d I dt Iodine decay + γ + γ X ( T ) 1/ = Σ f Xe 9.2 sec Fission γ Σ φ I f T fission yield X f T fission yield Cs λ I I λ X X C ( t ) φ ( t ) ( λ + σ φ ) X, eff Σ φ T = β λ X 135 natural natural decay X σ φ ax 2.3x10 decay T β ax ( t ) 6 T yr 135 σ axφt X X Ba ( stable) absorption decay

21 Fuel Loading Patterns

22 Burnable (absorbing) poisons Burnable poison forms products with lower adsorption cross sections, compensating for accumulation of other poisons. Boron and gadolinium oxides (gadolina) are examples.

23 Typical Control Worths

Chemical Engineering 693R

Chemical Engineering 693R Chemical Engineering 693R Reactor Design and Analysis Lecture 9 Neutron Kinetics Siritual hought 2 General ransient Problem Mono-energetic neutrons DD 2 φφ Σ aa φφ + SS vv For a reactor, SS ννσ ff φφ DD

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

Chemical Engineering 693R

Chemical Engineering 693R Chemical Engineering 693 eactor Design and Analysis Lecture 8 Neutron ransport Spiritual hought Moroni 7:48 Wherefore, my beloved brethren, pray unto the Father with all the energy of heart, that ye may

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

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

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

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

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

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

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

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

Reactor Operation with Feedback Effects

Reactor Operation with Feedback Effects 22.05 Reactor Physics - Part Twenty-Nine Reactor Operation with Feedback Effects 1. Reference Material: See pp. 368 372 in Light Water Reactor Control Systems, in Wiley Encyclopedia of Electrical and Electronics

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

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

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

Chemical Engineering 412

Chemical Engineering 412 Chemical Engineering 412 Introductory Nuclear Engineering Final Exam Review Spiritual Thought 2 Exam 3 Performance 3 Part a Part b Part c Part d Total Average 30.7 19.2 24.4 16.5 90.8 High 35.0 20.0 25.0

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

Reactivity Power and Temperature Coefficients Determination of the TRR

Reactivity Power and Temperature Coefficients Determination of the TRR Reactivity and Temperature Coefficients Determination of the TRR ABSTRACT Ahmad Lashkari Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran Tehran 14399-51113,

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

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

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

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

but mostly as the result of the beta decay of its precursor 135 I (which has a half-life of hours).

but mostly as the result of the beta decay of its precursor 135 I (which has a half-life of hours). 8. Effects of 135Xe The xenon isotope 135 Xe plays an important role in any power reactor. It has a very large absorption cross section for thermal neutrons and represents therefore a considerable load

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

"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

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

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

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

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

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

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

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

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

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

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

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

R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada

R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada REACTVTY CHANGES R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada Keywords: Reactivity Coefficient, Fuel Burnup, Xenon, Samarium, Temperature Contents 1. ntroduction

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

Numerical simulation of non-steady state neutron kinetics of the TRIGA Mark II reactor Vienna

Numerical simulation of non-steady state neutron kinetics of the TRIGA Mark II reactor Vienna arxiv:137.767v1 [physics.ins-det] 29 Jul 213 Numerical simulation of non-steady state neutron kinetics of the TRIGA Mark II reactor Vienna Julia Riede, Helmuth Boeck TU Wien, Atominstitut, A-12 Wien, Stadionallee

More information

PHYS-E0562 Ydinenergiatekniikan jatkokurssi Lecture 5 Burnup calculation

PHYS-E0562 Ydinenergiatekniikan jatkokurssi Lecture 5 Burnup calculation PHYS-E0562 Ydinenergiatekniikan jatkokurssi Lecture 5 Burnup calculation Jaakko Leppänen (Lecturer), Ville Valtavirta (Assistant) Department of Applied Physics Aalto University, School of Science Jaakko.Leppanen@aalto.fi

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

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

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

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

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

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

SUB-CHAPTER D.1. SUMMARY DESCRIPTION

SUB-CHAPTER D.1. SUMMARY DESCRIPTION PAGE : 1 / 12 CHAPTER D. REACTOR AND CORE SUB-CHAPTER D.1. SUMMARY DESCRIPTION Chapter D describes the nuclear, hydraulic and thermal characteristics of the reactor, the proposals made at the present stage

More information

Incineration of Plutonium in PWR Using Hydride Fuel

Incineration of Plutonium in PWR Using Hydride Fuel Incineration of Plutonium in PWR Using Hydride Fuel Francesco Ganda and Ehud Greenspan University of California, Berkeley ARWIF-2005 Oak-Ridge, TN February 16-18, 2005 Pu transmutation overview Many approaches

More information

The Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code

The Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code Journal of Nuclear and Particle Physics 2016, 6(3): 61-71 DOI: 10.5923/j.jnpp.20160603.03 The Effect of Burnup on Reactivity for VVER-1000 with MOXGD and UGD Fuel Assemblies Using MCNPX Code Heba K. Louis

More information

Development of 3D Space Time Kinetics Model for Coupled Neutron Kinetics and Thermal hydraulics

Development of 3D Space Time Kinetics Model for Coupled Neutron Kinetics and Thermal hydraulics Development of 3D Space Time Kinetics Model for Coupled Neutron Kinetics and Thermal hydraulics WORKSHOP ON ADVANCED CODE SUITE FOR DESIGN, SAFETY ANALYSIS AND OPERATION OF HEAVY WATER REACTORS October

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

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

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

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

Nuclear Fission. Q for 238 U + n 239 U is 4.??? MeV. E A for 239 U 6.6 MeV MeV neutrons are needed.

Nuclear Fission. Q for 238 U + n 239 U is 4.??? MeV. E A for 239 U 6.6 MeV MeV neutrons are needed. Q for 235 U + n 236 U is 6.54478 MeV. Table 13.11 in Krane: Activation energy E A for 236 U 6.2 MeV (Liquid drop + shell) 235 U can be fissioned with zero-energy neutrons. Q for 238 U + n 239 U is 4.???

More information

Laplace Transform Problems

Laplace Transform Problems AP Calculus BC Name: Laplace Transformation Day 3 2 January 206 Laplace Transform Problems Example problems using the Laplace Transform.. Solve the differential equation y! y = e t, with the initial value

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

MEASUREMENT AND COMPARISON OF CONTROL ROD WORTH OF BTRR USING INHOUR EQUATION AND PERIOD REACTIVITY CONVERSION TABLE

MEASUREMENT AND COMPARISON OF CONTROL ROD WORTH OF BTRR USING INHOUR EQUATION AND PERIOD REACTIVITY CONVERSION TABLE J. Bangladesh Acad. Sci., Vol. 41, No. 1, 95-103, 2017 MEASUREMENT AND COMPARISON OF CONTROL ROD WORTH OF BTRR USING INHOUR EQUATION AND PERIOD REACTIVITY CONVERSION TABLE MD. IQBAL HOSAN, M. A. M. SONER

More information

Closing the nuclear fuel cycle

Closing the nuclear fuel cycle Closing the nuclear fuel cycle Potential of the Gas Cooled Fast Reactor (GCFR) Godart van Gendt Physics of Nuclear Reactors (PNR) Department of R3 Faculty TNW TU Delft Supervisors: Dr. ir. W.F.G. van Rooijen

More information

u d Fig. 6.1 (i) Identify the anti-proton from the table of particles shown in Fig [1]

u d Fig. 6.1 (i) Identify the anti-proton from the table of particles shown in Fig [1] 1 (a) Fig. 6.1 shows the quark composition of some particles. proton neutron A B u u d u d d u d u u u u d Fig. 6.1 (i) Identify the anti-proton from the table of particles shown in Fig. 6.1. (ii) State

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

NPP Simulators for Education Workshop - Passive PWR Models

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

More information

Neutronic Calculations of Ghana Research Reactor-1 LEU Core

Neutronic Calculations of Ghana Research Reactor-1 LEU Core Neutronic Calculations of Ghana Research Reactor-1 LEU Core Manowogbor VC*, Odoi HC and Abrefah RG Department of Nuclear Engineering, School of Nuclear Allied Sciences, University of Ghana Commentary Received

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

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

Nuclear Theory - Course 227 FISSION PRODUCT POISONING

Nuclear Theory - Course 227 FISSION PRODUCT POISONING Nuclear Theory - Course 227 FISSION PRODUCT POISONING -All Fission-pro(i\lcts can.he. classitied as react or poi;sons because they all absorb neutrons to some extent. Most simply buildup slowly as the

More information

Cold Critical Pre-Experiment Simulations of KRUSTy

Cold Critical Pre-Experiment Simulations of KRUSTy Cold Critical Pre-Experiment Simulations of KRUSTy Kristin Smith * Rene Sanchez, Ph.D. * University of Florida, Nuclear Engineering Program Los Alamos National Lab, Advanced Nuclear Technology LA-UR-17-27250

More information

Fast Feedback Effects ofreactivity

Fast Feedback Effects ofreactivity Fast Feedback Effects ofreactivity Fuel Temperature Coolant Temperature Moderator Temperature Core Voiding Feedback - The Reactivity Chan~es as Power Changes When Power changes, the temperatures of reactor

More information

TRANSMUTATION OF CESIUM-135 WITH FAST REACTORS

TRANSMUTATION OF CESIUM-135 WITH FAST REACTORS TRANSMUTATION OF CESIUM-3 WITH FAST REACTORS Shigeo Ohki and Naoyuki Takaki O-arai Engineering Center Japan Nuclear Cycle Development Institute (JNC) 42, Narita-cho, O-arai-machi, Higashi-Ibaraki-gun,

More information

AN ABSTRACT OF THE THESIS OF. Justin R. Mart for the degree of Master of Science in Nuclear Engineering presented on June 14, 2013.

AN ABSTRACT OF THE THESIS OF. Justin R. Mart for the degree of Master of Science in Nuclear Engineering presented on June 14, 2013. AN ABSTRACT OF THE THESIS OF Justin R. Mart for the degree of Master of Science in Nuclear Engineering presented on June 14, 2013. Title: Feasibility Study on a Soluble Boron-Free Small Modular Reactor

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

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

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

Neutronic Issues and Ways to Resolve Them. P.A. Fomichenko National Research Center Kurchatov Institute Yu.P. Sukharev JSC Afrikantov OKBM,

Neutronic Issues and Ways to Resolve Them. P.A. Fomichenko National Research Center Kurchatov Institute Yu.P. Sukharev JSC Afrikantov OKBM, GT-MHR Project High-Temperature Reactor Neutronic Issues and Ways to Resolve Them P.A. Fomichenko National Research Center Kurchatov Institute Yu.P. Sukharev JSC Afrikantov OKBM, GT-MHR PROJECT MISSION

More information

EXPERIMENTAL DETERMINATION OF NEUTRONIC PARAMETERS IN THE IPR-R1 TRIGA REACTOR CORE

EXPERIMENTAL DETERMINATION OF NEUTRONIC PARAMETERS IN THE IPR-R1 TRIGA REACTOR CORE 2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 EXPERIMENTAL DETERMINATION

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

Year 11 Physics booklet Topic 1 Atomic structure and radioactivity Name:

Year 11 Physics booklet Topic 1 Atomic structure and radioactivity Name: Year 11 Physics booklet Topic 1 Atomic structure and radioactivity Name: Atomic structure and radioactivity Give a definition for each of these key words: Atom Isotope Proton Neutron Electron Atomic nucleus

More information

Chemical Engineering 412

Chemical Engineering 412 Chemical Engineering 412 Introductory Nuclear Engineering Lecture 7 Nuclear Decay Behaviors Spiritual Thought Sooner or later, I believe that all of us experience times when the very fabric of our world

More information

DEVELOPMENT OF REAL-TIME FUEL MANAGEMENT CAPABILITY AT THE TEXAS A&M NUCLEAR SCIENCE CENTER

DEVELOPMENT OF REAL-TIME FUEL MANAGEMENT CAPABILITY AT THE TEXAS A&M NUCLEAR SCIENCE CENTER DEVELOPMENT OF REAL-TIME FUEL MANAGEMENT CAPABILITY AT THE TEXAS A&M NUCLEAR SCIENCE CENTER A Thesis by NEIL AUBREY PARHAM Submitted to the Office of Graduate Studies of Texas A&M University in partial

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

Study on SiC Components to Improve the Neutron Economy in HTGR

Study on SiC Components to Improve the Neutron Economy in HTGR Study on SiC Components to Improve the Neutron Economy in HTGR Piyatida TRINURUK and Assoc.Prof.Dr. Toru OBARA Department of Nuclear Engineering Research Laboratory for Nuclear Reactors Tokyo Institute

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

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

Reactor Physics: Basic Definitions and Perspectives. Table of Contents

Reactor Physics: Basic Definitions and Perspectives. Table of Contents Reactor Physics - Basic Definitions and Perspectives Reactor Physics: Basic Definitions and Perspectives prepared by Wm. J. Garland, Professor, Department of Engineering Physics, McMaster University, Hamilton,

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

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

Chapter 2 Nuclear Reactor Calculations

Chapter 2 Nuclear Reactor Calculations Chapter 2 Nuclear Reactor Calculations Keisuke Okumura, Yoshiaki Oka, and Yuki Ishiwatari Abstract The most fundamental evaluation quantity of the nuclear design calculation is the effective multiplication

More information

REACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING WATER REACTORS (BWRs)

REACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING WATER REACTORS (BWRs) REACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING ATER REACTORS (BRs) Christophe Demazière Chalmers University of Technology Department of Reactor Physics SE-42 96 Gothenburg Sweden Abstract The loading

More information

Steady-State and Transient Neutronic and Thermal-hydraulic Analysis of ETDR using the FAST code system

Steady-State and Transient Neutronic and Thermal-hydraulic Analysis of ETDR using the FAST code system Steady-State and Transient Neutronic and Thermal-hydraulic Analysis of ETDR using the FAST code system Sandro Pelloni, Evaldas Bubelis and Paul Coddington Laboratory for Reactor Physics and Systems Behaviour,

More information

AP1000 European 11. Radioactive Waste Management Design Control Document

AP1000 European 11. Radioactive Waste Management Design Control Document CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated

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

11. Radioactive Waste Management AP1000 Design Control Document

11. Radioactive Waste Management AP1000 Design Control Document CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated

More information

Study of Control rod worth in the TMSR

Study of Control rod worth in the TMSR Nuclear Science and Techniques 24 (2013) 010601 Study of Control rod worth in the TMSR ZHOU Xuemei * LIU Guimin 1 Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China

More information

Available online at ScienceDirect. Energy Procedia 71 (2015 )

Available online at   ScienceDirect. Energy Procedia 71 (2015 ) Available online at www.sciencedirect.com ScienceDirect Energy Procedia 71 (2015 ) 97 105 The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4 High-Safety Fast Reactor Core Concepts

More information

OECD/NEA Transient Benchmark Analysis with PARCS - THERMIX

OECD/NEA Transient Benchmark Analysis with PARCS - THERMIX OECD/NEA Transient Benchmark Analysis with PARCS - THERMIX Volkan Seker Thomas J. Downar OECD/NEA PBMR Workshop Paris, France June 16, 2005 Introduction Motivation of the benchmark Code-to-code comparisons.

More information

«CALCULATION OF ISOTOPE BURN-UP AND CHANGE IN EFFICIENCY OF ABSORBING ELEMENTS OF WWER-1000 CONTROL AND PROTECTION SYSTEM DURING BURN-UP».

«CALCULATION OF ISOTOPE BURN-UP AND CHANGE IN EFFICIENCY OF ABSORBING ELEMENTS OF WWER-1000 CONTROL AND PROTECTION SYSTEM DURING BURN-UP». «CALCULATION OF ISOTOPE BURN-UP AND CHANGE IN EFFICIENCY OF ABSORBING ELEMENTS OF WWER-1000 CONTROL AND PROTECTION SYSTEM DURING BURN-UP». O.A. Timofeeva, K.U. Kurakin FSUE EDO «GIDROPRESS», Podolsk, Russia

More information

Research Article Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code

Research Article Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal at Zero Power Benchmark Cases with NODAL3 Code Hindawi Science and Technology of Nuclear Installations Volume 2017, Article ID 5151890, 8 pages https://doi.org/10.1155/2017/5151890 Research Article Analysis of NEA-NSC PWR Uncontrolled Control Rod Withdrawal

More information

D. Cano Ott Nuclear Innovation Nuclear Fission Division Dept. of Energy. CIEMAT-IFIC-UPC collaboration

D. Cano Ott Nuclear Innovation Nuclear Fission Division Dept. of Energy. CIEMAT-IFIC-UPC collaboration Beta-delayed neutron measurements for nuclear technologies D. Cano Ott Nuclear Innovation Nuclear Fission Division Dept. of Energy CIEMAT-IFIC-UPC collaboration i i B i GT K f i I ( Z, Q i ) T 1/ 2 K 1

More information

Study of Burnup Reactivity and Isotopic Inventories in REBUS Program

Study of Burnup Reactivity and Isotopic Inventories in REBUS Program Study of Burnup Reactivity and Isotopic Inventories in REBUS Program T. Yamamoto 1, Y. Ando 1, K. Sakurada 2, Y. Hayashi 2, and K. Azekura 3 1 Japan Nuclear Energy Safety Organization (JNES) 2 Toshiba

More information

Reactivity monitoring using the Area method for the subcritical VENUS-F core within the framework of the FREYA project

Reactivity monitoring using the Area method for the subcritical VENUS-F core within the framework of the FREYA project Reactivity monitoring using the Area method for the subcritical VENUS-F core within the framework of the FREYA project N. Marie 1, G. Lehaut 1, J.-L. Lecouey 1, A. Billebaud 2, S. Chabod 2, X. Doligez

More information