Lesson 14: Reactivity Variations and Control
|
|
- Godfrey Patrick
- 6 years ago
- Views:
Transcription
1 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 (Thermal Reactor) Long-term Variations Fuel Composition Changes with Burnup Means of Control Laboratory for Reactor Physics and Systems Behaviour Reactivity Variations and Control.. 1
2 General Different mechanisms cause variation of k eff, i.e. of reactivity Effects need to be compensated so as to maintain k eff = 1 Reactor power needs to be closely monitored and regulated (reactor control) In an anamolous situation, automatic reactor shutdown needs to be guaranteed Means of reactor control Poisons : neutron absorbers (control rods, burnable poisons, soluble poison, ) Refuelling (renewal of core loading) Auto-control mechanisms (limited possibilities) Reactivity Variations External causes (modification of poison, change of fuel, ) Internal causes (modifications in i values, and hence in neutron balance, ) Reactivity feedbacks Short-, medium-term effects (temperature, Xe, etc.) Long-term effects ( evolution of fuel composition) Reactivity Variations and Control.. 2
3 Reactivity Variations In reality, reactivity changes not sudden and constant, i.e. not step functions, function of time (also, spatial effects) kinetics eqns. need to be solved numerically Various time constants involved (e.g. time for power change to affect temperature, ) Values quite different for different types of feedbacks Short-term causes for -variation Fuel temperature (Doppler effect), < 1 sec (effect ~ prompt most important ) Moderator temperature, secs - mins Voidage of liquid moderator/coolant, secs (boiling, bubble formation, effect on density ) Medium-term causes Principal effect: Fission product Xe 135 in a thermal reactor, hours - days Long-term effects Fuel composition changes with irradiation (burnup), days - months Largest effect in power reactors ( burning of fissile, Pu-production, accumulation of FPs, ) Reactivity Variations and Control.. 3
4 Doppler Effect (T c ), Fuel Temp. Coeff Laboratory for Reactor Physics and Systems Behaviour When T c, U 238 resonances broadened due to increased thermal agitation of nuclei Area under resonance constant, but flux is less depressed Effective resonance integral, I eff In, where with Fuel Temperature Coefficient of Reactivity (Doppler Coeff.) Reactivity Variations and Control.. 4
5 Comments, c For a fast reactor, Doppler effect more difficult to calculate Very large number of resonances at high energies (very narrow, partly overlapping) Fissions also largely of resonance nature T c implies, e.g., increase of radiative captures in U 238, as well as of Pu 239 fissions Globally negative effect needs to be guaranteed Fissile enrichment (Pu-content) is limited Negative Doppler usually no problem (enough U 238 present), but if Pu-burner desired instead of a breeder, high Pu-contents needed (safety provides constraints ) Other effects of T c Fuel expansion (reduction of density: s, M 2 and leakage ) Important in small reactors, particularly fast reactors (fuel much more important for M 2 ) Reactivity Variations and Control.. 5
6 Moderator (Coolant) Temperature Coefficient, m m = Neutron spectrum effects Maxwellian part shifted to right when T m th s ~ 1/v (i.e. 1/ E ), but not exactly For, individual changes of important For U nat, c when T m In presence of Pu, this changes (Pu 239 resonance at 0.3 ev: +ive effect) Partly compensating effect from Pu 240 (large capture resonance at 1ev) Spectrum effect most important for solid moderator, e.g. graphite For a liquid moderator (coolant), density variation more important effect Undermoderation crucial for safety Reactivity Variations and Control.. 6
7 Void Coefficient, v v = (v : volumetric fraction of void ) Very important to have negative v for liquid moderator/coolant (Chernobyl!) Boiling implies a strong reduction of density As for m, thermal reactor needs to be undermoderated Sodium (coolant) voidage in fast reactor complex effects Moderation reduced, spectrum harder ( E ) Pu : positive effect Na absorptions : positive effect Na density neutron leakage : negative effect Effect particularly important for small reactors, or for pancake cores In practice, for a sodium-cooled fast reactor, v often slightly positive Not serious, because c negative and has more immediate impact Reactivity Variations and Control.. 7
8 Comments For the short-term effects, one may write: However, this does not give the true dynamic behaviour No consideration of the time constants One needs proper time-dependent modelling of the power reactor (including the secondary cooling system), with coupling betn. neutronics, thermal-hydraulics Safety studies: Numerical simulation and analysis of hypothetical accident situations In general, if all the s are negative, reactor inherently safe from viewpoint of automatic shutdown Calculation of s generally very delicate Compensation of individual effects, e.g. sodium v, or m in HTR (graphite) Necessary to carry out checks on power reactor before start-up Reactivity Variations and Control.. 8
9 Consequences for Reactor Control Strongly negative s demand large reactivity reserve Complex control system (economics aspect) Laboratory for Reactor Physics and Systems Behaviour After reactor shut-down, one needs to be able to compensate the important s corresponding to different reactor states: (1) Hot full power (HFP) (2) Hot zero power (HZP) (3) Cold zero power (CZP) For such considerations, one may use: Reactivity Variations and Control.. 9
10 Medium-term Reactivity Variations Laboratory for Reactor Physics and Systems Behaviour For a power reactor, the FP s accumulate and influence the neutron balance In general, long-term poisoning effect (~ 50 b extra a added per fission (thermal reactor)) Special case (thermal reactor) ~ 2-3 days after start-up, one obtains an equilibrium Reactivity Variations and Control.. 10
11 Efect of a Poison on In, the FP s (thermal reactor) mainly influence f One has (1) For a large reactor, (2) From (1) and (2), Reactivity Variations and Control.. 11
12 Equilibrium-Xenon Poisoning At equilibrium, Laboratory for Reactor Physics and Systems Behaviour Equilibrium-Xe effect depends on Ex. For a system with U 235 as fuel (p = = 1), By far, most important FP effect in a thermal reactor Reactivity Variations and Control.. 12
13 Xenon Transients Equilibrium betn. production, destruction mechanisms: If reactor is shutdown, destruction by absorption stops, but principal production (I 135 decay) continues At equilibrium, After t = 0, For a reactor at high power, it is possible that the reactivity reserve is insufficient for restarting very soon after the shutdown Reactivity Variations and Control.. 13
14 Comments Changes in reactor power produce reactivity variations due to xenon In large-sized reactors, one has possibility of xenon oscillations Instabilities, not serious quite large time constant N.B.: Another quite important, individual FP: Sm 149 (stable, more of a long-term effect ) Reactivity Variations and Control.. 14
15 Long-term Effects -variation of largest magnitude in power reactor, also slowest (not really, kinetics ) Fuel composition changes with burnup (fuel evolution ) Determines, for given initial -excess, max. burnup achievable (from neutronics viewpoint) Involved phenomena: Consumption of fissile material (U 235, ) Production of new fissile material from fertile (Pu 239 from U 238, etc.) Appearance of non-fissile nuclides such as U 236 ( also transuraniums ) Accumulation of stable FP s All the above (except 2 nd ) cause One needs to determine the fuel composition as function of irradiation time, via Fuel Evolution Equations (Bateman Equations) analysis, corresponding to each different reactor state, gives new values for: k eff, -coefficients, control rod worths, power distribution, etc. Reactivity Variations and Control.. 15
16 Fuel Evolution Equations For thermal reactor burning enr. U : Even if power is constant, (t) varies because of variation of f Preferable to consider the variable fluence (time-integrated flux): Equation for U 235 becomes with solution: (units: cm -2 ) (analogy with radioactive decay : time, a5 : decay constant) Considering other reactions, one has for the other nuclides etc., etc. N.B.: For the fissiles, a = c + f Reactivity Variations and Control.. 16
17 Comments For the FP s, fuel evolution equations more complex Radioactive decay chains also need to be considered Only few FP s need to be treated explicitly Fuel burnup: (contributions of all fissile isotopes to be considered) Average values: One can express all parameters ( k eff, -coefficients, etc.) in function of W sp Reactivity Variations and Control.. 17
18 Example LWR fuel ~ 3.4% U enr W sp ~ 30,000 MWd/t (today, > 4% enr, W sp ~ 50,000 MWd/t) Solution of Fuel Evolution Equations gives In example, ~ 30% of fissions in Pu (in-situ) For a U nat reactor (CANDU) can be ~ 50% Pu- quality at discharge (~ 70% fissile) poor for nuclear explosive ( civil Pu ) For production of military Pu, one needs to strongly reduce W sp (< 5000 MWd/t) Nuclear power plants too costly for this (one uses cold power reactors) Reactivity Variations and Control.. 18
19 Consequences for Reactor Control Laboratory for Reactor Physics and Systems Behaviour For considered example (U enr, LWR): For a U nat reactor (CANDU, ): N.B.: Scales different Large reactivity variation in LWR case demands partial charging, discharging of core e.g. with 3 segments (zones) in the equilibrium situation: 1 new fuel (at t = 0) 2 fuel with one cycle of residence in core 3 fuel with 2 cycles of residence Reactivity Variations and Control.. 19
20 Consequences for Control (contd.) Laboratory for Reactor Physics and Systems Behaviour After time T/3, one discharges Segment 3 and displaces the fuel between the zones Reactivity variation: Reactivity Variations and Control.. 20
21 Comments Reactivity variation reduced by factor of ~ 3 (in case considered) Initial enrichment needed ( as also control ), significantly reduced Fuelling, refuelling needed more frequently (but each time quantity ~ 1/3) In the limit, one can have continuous refuelling (not possible in LWR ) One can profit also from flux flattening Material properties deteriorate with irradiation One has technological constraints to maximum burnup in LWRs (fuel, cladding), i.e. increase in enrichment not meaningful beyond certain value For systems using U nat, neutronics provides principal constraint to burnup (even with on-line refuelling, as in CANDU) Reactivity Variations and Control.. 21
22 Means of Control Control rods (of different types) Compensation rods, e.g. for Xe-buildup, cold-to-hot, etc. Higly absorbing materials (B 4 C, Ag-In-Cd, ) Pilot rods, for power regulation, automatic piloting, etc. (low -worths, steel often used) Safety rods, (normally withdrawn, fall rapidly in accidental situation ( scram ), B 4 C, etc. Soluble poison (liquid moderator/coolant) For long-term effects, adjustable concentration (H 3 BO 3 in PWRs) Not used in BWRs (influence too large on v ) Reduces need for compensation control rods (advantage also of better power distribution) Requires special chemical processes and control Burnable poison Solid, strong absorbers (Gd, B, ), mixed with a certain fraction of fuel rods (BWRs, ) Disappears (is burnt) during irradiation, with density reduction: Again, mainly for long-term effects (fuel evolution) Can be optimised to flatten -curve (cf. Slide 19) Reactivity Variations and Control.. 22
23 Reactor Instrumentation, Power Regulation Power of NPP known via thermal balance for coolant, bur power regulation needs rapid monitoring (possible via neutron flux measurements, with prior calibration ) Neutron detectors: fission chambers, BF 3 counters, etc. (with, without -compensation) Start-up chains (< 10-6 P 0 ) Minimal count-rate necessary at start (sensitive detectors, external n-source if necessary ) Logarithmic chains (~ 10-7 P 0 to P 0 ) Several decades covered, current mode; derivative provides period measurement Linear chains (~ 10-2 P 0 to 10 P 0 ), for piloting reactor Allow fine regulation; feedback loop (connected to pilot rods) and servo-mechanism Safety chains, for triggering insertion of safety rods (often in mode 2-out-of-3 ) Fixed criteria, e.g. P 1.15 P 0, T T min, N.B.: Detectors often in reflector; however NPPs also have in-core instrumentation, e.g. series of miniature chambers, which can provide a detailed flux map. Reactivity Variations and Control.. 23
24 Summary, Lesson 14 External, internal reactivity variations Short-term variations Reactivity feedbacks (fuel temperature, moderator temperature, coolant voidage, etc.) Importance for inherent safety Medium-term variations Xe 135 poisoning (equilibrium, transients, ) Long-term variations Fuel composition changes with burnup Evolution equations Consequences for control Means of control, instrumentation Reactivity Variations and Control.. 24
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 informationLecture 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 informationLectures 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 informationCANDU 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 informationChem 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 informationThe 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 informationReactivity 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 informationNuclear 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 informationAdvanced 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 informationIntroduction 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 informationReactor 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 information20.1 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 informationNeutron 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 information3. 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 informationXenon 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 informationShutdown 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 informationFigure 22.1 Unflattened Flux Distribution
22 Neutron Flux Control If nothing were done to flatten the flux in our reactors, it would look something like Figure 22.1. The flux would be a maximum in the efuel of the reactor (where neutrons are moving
More informationFundamentals 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 informationbut 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 informationChemical 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 informationReactor 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 informationSolving 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 informationLecture 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 informationXV. 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 informationChapter 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 informationLectures 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 informationNuclear 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 informationOperational 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 informationNuclear 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 informationHybrid Low-Power Research Reactor with Separable Core Concept
Hybrid Low-Power Research Reactor with Separable Core Concept S.T. Hong *, I.C.Lim, S.Y.Oh, S.B.Yum, D.H.Kim Korea Atomic Energy Research Institute (KAERI) 111, Daedeok-daero 989 beon-gil, Yuseong-gu,
More informationNuclear 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 informationElements, 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 informationThe 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 informationR.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 informationSUB-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 informationSubcritical 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 informationOECD/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 informationChain 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 informationFundamentals of Nuclear Power. Original slides provided by Dr. Daniel Holland
Fundamentals of Nuclear Power Original slides provided by Dr. Daniel Holland Nuclear Fission We convert mass into energy by breaking large atoms (usually Uranium) into smaller atoms. Note the increases
More informationPHYS-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 informationNeutronic 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 informationREACTOR 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 informationFast 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 informationControl 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 informationStudy 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 informationPower Installations based on Activated Nuclear Reactions of Fission and Synthesis
Yu.V. Grigoriev 1,2, A.V. Novikov-Borodin 1 1 Institute for Nuclear Research RAS, Moscow, Russia 2 Joint Institute for Nuclear Research, Dubna, Russia Power Installations based on Activated Nuclear Reactions
More informationThe 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 informationDelayed 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 informationNuclear Power MORE CHAPTER 11, #6. Nuclear Fission Reactors
MORE CHAPTER 11, #6 Nuclear Power Nuclear Fission Reactors The discovery that several neutrons are emitted in the fission process led to speculation concerning the possibility of using these neutrons to
More informationMA/LLFP Transmutation Experiment Options in the Future Monju Core
MA/LLFP Transmutation Experiment Options in the Future Monju Core Akihiro KITANO 1, Hiroshi NISHI 1*, Junichi ISHIBASHI 1 and Mitsuaki YAMAOKA 2 1 International Cooperation and Technology Development Center,
More informationTask 3 Desired Stakeholder Outcomes
Task 3 Desired Stakeholder Outcomes Colby Jensen IRP Kickoff Meeting, Nov 19-20, 2015 Instrumentation Overview Three general levels of core instrumentation: Reactor control and operation Additional reactor
More information22.05 Reactor Physics Part Five. The Fission Process. 1. Saturation:
22.05 Reactor Physics Part Five The Fission Process 1. Saturation: We noted earlier that the strong (nuclear) force (one of four fundamental forces the others being electromagnetic, weak, and gravity)
More informationReactors 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 informationNuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region. J.N. Wilson Institut de Physique Nucléaire, Orsay
Nuclear Data for Reactor Physics: Cross Sections and Level Densities in in the Actinide Region J.N. Wilson Institut de Physique Nucléaire, Orsay Talk Plan Talk Plan The importance of innovative nuclear
More informationA 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 informationTHORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR
International Conference Nuclear Energy for New Europe 2005 Bled, Slovenia, September 5-8, 2005 ABSTRACT THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR Boris Bergelson, Alexander Gerasimov Institute
More informationMechanical 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 informationINTRODUCTION 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 informationThorium as a Nuclear Fuel
Thorium as a Nuclear Fuel Course 22.251 Fall 2005 Massachusetts Institute of Technology Department of Nuclear Engineering 22.351 Thorium 1 Earth Energy Resources Commercial Energy Resources in India Electricity
More informationLesson 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 informationCRITICAL 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 informationNuclear 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 informationFuel cycle studies on minor actinide transmutation in Generation IV fast reactors
Fuel cycle studies on minor actinide transmutation in Generation IV fast reactors M. Halász, M. Szieberth, S. Fehér Budapest University of Technology and Economics, Institute of Nuclear Techniques Contents
More informationThe Physics of Nuclear Reactors. Heather King Physics 420
The Physics of Nuclear Reactors Heather King Physics 420 Nuclear Reactions A nuclear reaction is a reaction that involves atomic nuclei, or nuclear particles (protons, neutrons), producing products different
More informationIncineration 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 informationReactor 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 informationChapter 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 informationThe influence of thorium on the temperature reactivity. coefficient in a 400 MWth pebble bed high temperature. plutonium incinerator reactor
The influence of thorium on the temperature reactivity coefficient in a 400 MWth pebble bed high temperature plutonium incinerator reactor G. A. Richards Project-based mini-dissertation (Option C) for
More information17 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 informationFission Reactors. Alternatives Inappropriate. Fission Reactors
Page 1 of 5 Fission Reactors The Polywell Reactor Nuclear Reactions Alternatives Inappropriate Hidden Costs of Carbon Web Site Home Page Fission Reactors There are about 438 Neutron Fission Power Reactors
More informationNuclear Theory - Course 227 EFFECT OF FUEL BURNUP
Nuclear Theory - Course 227 EFFECT OF FUEL BURNUP The changes in the composition of the fuel as it is depleted give rise to a number of effects which may be described under the following headings: 1) Long
More informationPHYSICS 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 informationCHAPTER NEUTRON DETECTORS
73 CHAPTER 6 CONTROL AND OPERATONS The basic and unique dynamic characteristics associated with the reactor core have been discussed in the preceding chapter; here we will focus upon certain reactor core
More information(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 informationChemical 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 informationN 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 informationAN 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 informationMONTE 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 information1. Which is the most commonly used molten metal for cooling of nuclear reactors? A. Zinc B. Sodium C. Calcium D. Mercury
1. Which is the most commonly used molten metal for cooling of nuclear reactors? A. Zinc B. Sodium C. Calcium D. Mercury 2. Commercial power generation from fusion reactor is not yet possible, because
More informationNUCLEAR ENGINEERING. 6. Amongst the following, the fissionable materials are (a) U233andPu239 (b) U23iandPu233 (c) U235andPu235 (d) U238andPu239
NUCLEAR ENGINEERING 1. The efficiency of a nuclear power plant in comparsion to a conventional thermal power plant is (a) same (b) more (c) less (d) may be less or mote depending on size (e) unpredictable.
More informationPWR CONTROL ROD EJECTION ANALYSIS WITH THE MOC CODE DECART
PWR CONTROL ROD EJECTION ANALYSIS WITH THE MOC CODE DECART Mathieu Hursin and Thomas Downar University of California Berkeley, USA mhursin@nuc.berkeley.edu,downar@nuc.berkeley.edu ABSTRACT During the past
More informationR.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada
NUCLEAR REACTOR CONFIGURATION R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada Keywords: Nuclear Reactors, Reactor Types, Reactor Arrangement, Technical Data Contents
More informationCiclo combustibile, scorie, accelerator driven system
Ciclo combustibile, scorie, accelerator driven system M. Carta, C. Artioli ENEA Fusione e Fissione Nucleare: stato e prospettive sulle fonti energetiche nucleari per il futuro Layout of the presentation!
More informationLectures 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 informationSafety Analysis of Loss of Flow Transients in a Typical Research Reactor by RELAP5/MOD3.3
International Conference Nuclear Energy for New Europe 23 Portorož, Slovenia, September 8-11, 23 http://www.drustvo-js.si/port23 Safety Analysis of Loss of Flow Transients in a Typical Research Reactor
More informationDESIGN 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 informationLectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 6
Lectures on Nuclear Power Safety Lecture No 6 Title: Introduction to Thermal-Hydraulic Analysis of Nuclear Reactor Cores Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture
More informationThe Diablo Canyon NPPT produces CO 2 -free electricity at half the state s (CA) average cost
ECE_Energy for High-Tech Society 1 The Diablo Canyon NPPT produces CO 2 -free electricity at half the state s (CA) average cost Nuclear Energy: Power for a High-Tech Society ECE_Energy for High-Tech Society
More informationDevelopment 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 informationQuestion to the class: What are the pros, cons, and uncertainties of using nuclear power?
Energy and Society Week 11 Section Handout Section Outline: 1. Rough sketch of nuclear power (15 minutes) 2. Radioactive decay (10 minutes) 3. Nuclear practice problems or a discussion of the appropriate
More informationTRANSMUTATION 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 informationLecture 13. Applications of Nuclear Physics Fission Reactors and Bombs Overview
Lecture 13 Applications of Nuclear Physics Fission Reactors and Bombs Dec 2006, Lecture 13 Nuclear Physics Lectures, Dr. Armin Reichold 1 12.1 Overview 12.1 Induced fission Fissile nuclei Time scales of
More informationAvailable 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 informationULOF Accident Analysis for 300 MWt Pb-Bi Coolled MOX Fuelled SPINNOR Reactor
ULOF Accident Analysis for 300 MWt Pb-Bi Coolled MOX Fuelled SPINNOR Reactor Ade afar Abdullah Electrical Engineering Department, Faculty of Technology and Vocational Education Indonesia University of
More informationWorking Party on Pu-MOX fuel physics and innovative fuel cycles (WPPR)
R&D Needs in Nuclear Science 6-8th November, 2002 OECD/NEA, Paris Working Party on Pu-MOX fuel physics and innovative fuel cycles (WPPR) Hideki Takano Japan Atomic Energy Research Institute, Japan Introduction(1)
More informationWe are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors
We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists 3,700 108,500 1.7 M Open access books available International authors and editors Downloads Our
More informationSIMULATION OF LEAKING FUEL RODS
SIMULATION OF LEAKING FUEL RODS Zoltán Hózer KFKI Atomic Energy Research Institute P.O.B. 49, H-1525 Budapest, Hungary Hozer@sunserv.kfki.hu Abstract The behaviour of failed fuel rods includes several
More informationPHYSICS FOR RADIATION PROTECTION
PHYSICS FOR RADIATION PROTECTION JAMES E. MARTIN School of Public Health The University of Michigan A Wiley-Interscience Publication JOHN WILEY & SONS, INC. New York Chichester Weinheim Brisbane Singapore
More informationThe Effect of 99 Mo Production on the Neutronic Safety Parameters of Research Reactors
The Effect of 99 Mo Production on the Neutronic Safety Parameters of Research Reactors Riham M. Refeat and Heba K. Louis Safety Engineering Department, Nuclear and Radiological Regulation Authority (NRRA),
More informationREACTOR PHYSICS FOR NON-NUCLEAR ENGINEERS
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) Rio de Janeiro, RJ, Brazil, May 8-12, 2011, on CD-ROM, Latin American Section (LAS)
More information