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

Size: px
Start display at page:

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

Transcription

1 enon Effects B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec September 1

2 Contents We study the importance of e-135 in the operation of nuclear reactors September 2

3 Effects of enon Poison Saturating fission products are fission products whose concentration in fuel operating in a steady flux (i.e., at steady power): depends on the flux level, and comes to an asymptotic, finite limit even as the value of the steady flux is assumed to increase to infinity. The most important saturating fission product is 135 e, but other examples are 103 Rh, 149 Sm and 151 Sm. n each case the nuclide is a direct fission product, but is also produced by the -decay of another fission product September 3

4 135 e and e is produced directly in fission, but mostly from the beta decay of its precursor 135 (half-life hours). t is destroyed in two ways: By its own radioactive decay (half-life hours), and By neutron absorption to 136 e. See Figure 135 e/ 135 Kinetics in next slide September 4

5 -135/e-135 Kinetics We will see that production of 135 e by beta decay of 135 dominates over its direct production in fission. Fissions -( 1/2 =18 s) 135 Te 135 -( 1/2 =6.585 h) -( 1/2 =9.169 h) 135 e Burnout by neutron absorption 2015 September 5

6 135 e and e has a very important role in the reactor t has a very large thermal-neutron absorption cross section t is a considerable load on the chain reaction ts concentration has an impact on power distribution, but in turn is affected by the power distribution, by movement of reactivity devices, and significantly by changes in power September 6

7 135 e and 135 (cont d) The large absorption cross section of 135 e plays a significant role in the overall neutron balance and directly affects system reactivity, both in steady state and in transients. t also influences the spatial power distribution in the reactor. The limiting absorption rate at extremely high flux maximum steady-state reactivity load ~ -30 mk. n CANDU, the equilibrium load at full power ~ -28 mk (see Figure) 2015 September 7

8 The Equations for -135/e-135 Kinetics First, define symbols: Let and be the -135 and e-135 concentrations in the fuel. Let and be the -135 and e-135 decay constants, and Let and be their direct yields in fission Let be the e-135 microscopic absorption cross section Let be the neutron flux in the fuel, and Let f be the fuel fission cross section 2015 September 8

9 Differential Equations for Production and Removal -135 has 1 way to be produced, and 1 way to disappear, whereas e-135 has 2 ways to be produced, and 2 ways to disappear The differential equations for the production and removal vs. time t can then be written as follows: d dt f (1) d dt f (2) 2015 September 9

10 Steady State Use Subscript ss n steady state the derivatives are zero: f ss ss 0 (3) ss f ss ss ss ss 0 (4) 2015 September 10

11 Steady State Solve Eq. (3) for steady-state -135 concentration ss : ss fss Substitute this in Eq. (4): (5) ss ss ss f ss f ss Now solve this for steady-state e-135 concentration ss : ss f ss ss 2015 September 11

12 nteractive Discussion/Exercise What is the difference in character between the equations for the e and steady-state concentrations? 2015 September 12

13 ss fss Steady State Final Equations The steady-state -135 concentration is directly proportional to the flux value Whereas fss ss (6) ss ss is not proportional to the flux, in fact it saturates in high flux: n the limit where goes to infinity: (5) ss ( steady state, very high flux ) f (7) 2015 September 13

14 Typical Values Typical values of the parameters: -135 half-life = h = 2.92*10-5 s -1 e-135 half-life = h = 2.10*10-5 s -1 = = ( depends on the fuel burnup, because the e-135 yields from U-235 and Pu-239 fission are quite different) = 3.20*10-18 cm 2 [that s 3.2 million barns!] [ depends on temperature] f = cm -1, and For full power in CANDU, ss,fp = 7.00*10 13 n.cm -2 s September 14

15 Values at Steady State f we substitute these numbers into Eqs. (5) and (6), we find that at steady-state full power: ss,fp = 3.06*10 14 nuclides.cm -3 (8) ss,fp = 3.79*10 13 nuclides.cm -3 (9) With these values we note that at steady-state full power ss, fp f ss, fp 2.92*10 5 s 1 *3.06* *0.002cm 1 14 cm 3 *7.0* *10 13 cm 2 s 9 1 cm 3. s *10 8 cm 3. s 1 Therefore at steady-state full power the e-135 comes very predominantly (96%) from -135 decay rather than directly from fission! 2015 September 15

16 Values at Steady State Also at steady-state full power ss, fp ss, fp 2.1*10 ss, fp 5 s 8.48* *10 9 *3.78*10 18 cm cm 3. s 2 1 Therefore, at steady-state full power, the e-135 disappears very predominantly (91%) from burnout (by neutron absorption) rather than from decay! 13 cm 3 *3.79* *10 cm 3 8 cm 3 *7.0*10. s 13 1 cm 2. s September 16

17 Values at Steady State with Very High Flux n the limit where ss is very large (goes to infinity), we find from Eq.(7) i. e, ss, the e *10 Comparing Eq.(8) with ss, fp 0.92* 135 is f ss, 92% *0.002 this value, saturated 4.11*10 we at find full 13 nuclides. cm power 3 (10) (11) 2015 September 17

18 2015 September 18 e-135 Load = e-135 Reactivity Effect , * *3.79*10 3.2*10 1, : * *,. 2 '. 135., sec 135, 2,, 13 18,, 2 2,, 2 2, ,, 2 2, , 2 mk is value accurate A more estimate an is This mk k k k and k and k reactor critical from a Starting k k form a similar would have k in change The k k to change the apply we f k for formula group the recalling by effect reactivity s xenon the of estimate an get can We is contribution e The tion cross absorption thermal the mostly affects e fp eff eff eff fp eff fp ss eff eff a a eff eff a a a f a a a a a a f a a

19 e-135 Load in Various Conditions The most accurate value for the steady-state e-135 load in CANDU at full power is,fp = -28 mk (12) n any other condition, when the e-135 concentration is different from the steady-state full-power value (e.g., in a transient), we can determine the e-135 load by using the ratio of the instantaneous value of to ss,fp: *, fp 28 mk * 28 mk * *10 cm ss, fp ss, fp (13) The instantaneous e-135 concentration would of course have to be determined, say by solving the differential e-135/-135 kinetics equations (1)-(2) September 19

20 Excess e-135 Load We may sometimes like to quote not the absolute e-135 load, but instead the excess xenon load, i.e., the difference from its reference steady-state value (-28 mk), Using Eq.(13) in the previous slide: Excess or " Additional " e 135 Load, fp 28* 1 mk *10 (14) 2015 September 20

21 Equilibrium enon Load Figure Credit: Nuclear Reactor Kinetics, by D. Rozon, Polytechnic nternational Press, September 21

22 Effects of 135 e on Power Distribution High-power bundles have a higher e-135 concentration, i.e., a higher xenon load, therefore a lower local reactivity xenon flattens the power distribution n steady state, 135 e reduces maximum bundle and channel powers by ~ 5% and 3% respectively September 22

23 Saturating-Fission-Product-Free Fuel n fresh bundles entering the reactor, 135 e and other saturating fission products will build up (see Figure). The reactivity of fresh bundles drops in the first few days, as saturating fission products build in. Saturating-fission-product-free fuel will have higher power for the first hours and days than immediately later the effect may range up to ~10% on bundle power, and ~5% on channel power September 23

24 Build-up of 135 e in Fresh Fuel Figure Credit: Nuclear Reactor Kinetics, by D. Rozon, Polytechnic nternational Press, September 24

25 Saturating-Fission-Product-Free Fuel For an accurate assessment of powers after refuelling, calculations of the nuclear properties need to be performed at close intervals (a few hours) to capture the build-up of saturaring fission products, or else a phenomenological correction of the properties of fresh bundles needs to be made September 25

26 Effect of Power Decrease on 135 e Concentration The e-135 concentration changes significantly in power changes, and this has very strong effects on the system reactivity. When power is reduced from a steady level: The burnout rate of 135 e is decreased in the reduced flux, but 135 e is still produced by the decay of 135 the 135 e concentration increases at first But the 135 production rate is decreased in the lower flux, therefore the 135 inventory starts to decrease The 135 decay rate decreases correspondingly the 135 e concentration reaches a peak, then starts to decrease - see Figure. The net result is that there is an initial decrease in core reactivity; the reactivity starts to turn around after the xenon reaches its peak September 26

27 enon Reactivity Transients Following Setback to Various Power Levels e Reactivity (mk) vs. Time (h): Step Change from FP to 80% FP September 27

28 enon Reactivity Transients Following Setback to Various Power Levels E+01 e Reactivity (mk) vs. Time (h): Step Change from FP to 60% FP E E E E E E E September 28

29 enon Reactivity Transients Following Setback to Various Power Levels e Reactivity (mk) vs. Time (h): Step Change from FP to 40% FP September 29

30 enon Transient Following a Shutdown A reactor shutdown presents the same scenario in an extreme version: there is a very large initial increase in 135 e concentration and decrease in core reactivity. f the reactor is required to be started up shortly after shutdown, extra positive reactivity must be supplied, if possible, by the Reactor Regulating System. The 135 e growth and decay following a shutdown in a typical CANDU is shown in the next Figure September 30

31 enon Transient Following Reactor Shutdown 2015 September 31

32 enon Transient Following a Shutdown t can be seen that, at about 10 hours after shutdown, the (negative) reactivity worth of 135 e has increased to several times its equilibrium full-power value. At ~35-40 hours the 135 e has decayed back to its pre-shutdown level. f it were not possible to add positive reactivity during this period, every shutdown would necessarily last some 40 hours, when the reactor would again reach criticality September 32

33 enon Override To achieve xenon override and permit power recovery following a shutdown (or reduction in reactor power), positive reactivity must be supplied to override xenon growth; e.g., the adjuster rods can be withdrawn to provide positive reactivity. t is not possible to provide complete xenon override capability; this would require > 100 mk of positive reactivity. The CANDU-6 adjuster rods provide approximately 15 milli-k of reactivity, which is sufficient for about 30 minutes of xenon override following a shutdown September 33

34 Case of Power ncrease Conversely to the situation in a power reduction, when power is increased the 135 e concentration will first decrease, and then go through a minimum. Then it will rise again to a new saturated level (if power is held constant at the higher value). However, one point to remember is that e-135 changes following power changes provide positive feedback. Large reactors may be unstable with respect to xenon changes above a certain power level September 34

35 Solution of e- Kinetics After a Shutdown The differential equations for e-135/-135 kinetics are: d f (15) dt d f (16) dt n a transient (non-steady-state) situation, these equations can be numerically integrated to find the evolution of and, starting from known initial conditions 0 and September 35

36 Case of an nstantaneous Shutdown f the reactor is subjected to an instantaneous shutdown, we can solve Eqs. (15) and (16) analytically. f the flux 0 at t = 0, the terms containing disappear, and the equations simplify to: d dt d dt (17) (18) The solution of Eq. (17) is immediate: decays according to the exponential-decay law: 0 e t (19) 2015 September 36

37 2015 September 37 nstantaneous Shutdown Solving for Eq.(18) for becomes., (21).(19) int 10 (20). exp (19) 0 0 separately out balance must e and e in terms the t all for equality a n be to this for order n Be Ae e e B e A yields Eq o form the Substituting Be Ae try So e and form e the of onentials contain may for solution the that suggest and e in terms The e dt d t t t t t t t t t t t

38 2015 September 38 nstantaneous Shutdown Solving for (18)!].(17) [ (11) (5) : (10) 0 :.(7), min det. inf, (9), Eqs satisfy indeed these that to verify you to it leave e e e solution full the have we Therefore A B B A t condition initial the and Eq to resort we B e er To B on ormation no balance already e in terms The A A A get we e the Balancing t t t t t

39 nstantaneous Shutdown - Numerics t will be left as an exercise to evaluate and, and the corresponding reactivity effect, for a time period following a reactor shutdown, using the initial conditions of a steady state at various powers September 39

40 enon Oscillations enon oscillations are an extremely important scenario to guard against in reactor design and operation. magine that power rises in part of the reactor (say one half), but the regulating system keeps the total power constant (as its mandate normally requires). Therefore the power must decrease in the other half of the reactor. The changes in power in different directions in the two halves of the reactor will set off changes in 135 e concentration, but in different directions, in the two reactor halves. cont d 2015 September 40

41 enon Oscillations (cont d) The 135 e concentration will increase in the reactor half where the power is decreasing. t will decrease in the half where the power is increasing. These changes will induce positive-feedback reactivity changes (why?). Thus, the e and power changes will be amplified (at first) by this positive feedback! cont d 2015 September 41

42 enon Oscillations (cont d) f not controlled, the effects will reverse after many hours (just as we have seen in the xenon transients in the earlier slides). enon oscillations may ensue, with a period of ~20-30 h. These may be growing oscillations the amplitude will increase! [Are xenon oscillations completely hypothetical, or can they really happen? What daily perturbation can set off such transients?] cont d 2015 September 42

43 enon Oscillations (cont d) Large reactors, at high power (where 135 e reactivity is important) are unstable with respect to xenon! This is exacerbated in cores which are more decoupled (as in CANDU). t s the zone controllers which dampen/remove these oscillations that s one of their big jobs (spatial control)! 2015 September 43

44 END 2015 September 44

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 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

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

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

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

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

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

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

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

B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2: Fission and Other Neutron Reactions B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 2015 Sept.-Dec. 2015 September 1 Contents Concepts: Fission and other

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

Energy Dependence of Neutron Flux

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

More information

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

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

Chemical Engineering 412

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

More information

Reactor 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 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

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

8: Source-Sink Problems in 1 Energy Group

8: Source-Sink Problems in 1 Energy Group 8: Source-Sink Problems in 1 Energy Group B. Rouben McMaster University Course EP 4D03/6D03 Nuclear Reactor Analysis (Reactor Physics) 015 Sept.-Dec. 015 September 1 Contents Solving the 1-group diffusion

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

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

Figure 22.1 Unflattened Flux Distribution

Figure 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 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

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

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

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

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

2. The Steady State and the Diffusion Equation

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

More information

Nuclear Theory - Course 227 EFFECT OF FUEL BURNUP

Nuclear 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 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

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

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

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

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

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

More information

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

FUEL PERFORMANCE EVALUATION THROUGH IODINE ACTIVITY MONITORING K.ANANTHARAMAN, RAJESH CHANDRA

FUEL PERFORMANCE EVALUATION THROUGH IODINE ACTIVITY MONITORING K.ANANTHARAMAN, RAJESH CHANDRA 6A-46 FUEL PERFORMANCE EVALUATION THROUGH IODINE ACTIVITY MONITORING K.ANANTHARAMAN, RAJESH CHANDRA CA9800600 Refuelling Technology Division Bhabha Atomic Research Centre Bo m ba,-4000 85,INDIA ABSTRACT

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

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

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

Introduction to Nuclear Engineering. Ahmad Al Khatibeh

Introduction to Nuclear Engineering. Ahmad Al Khatibeh Introduction to Nuclear Engineering Ahmad Al Khatibeh CONTENTS INTRODUCTION (Revision) RADIOACTIVITY Radioactive Decay Rates Units of Measurement for Radioactivity Variation of Radioactivity Over Time.

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

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

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

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

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

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

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

Comparative Safety Evaluation of Thorium Fuel to. Natural Uranium Fuel in a CANDU 6 Reactor

Comparative Safety Evaluation of Thorium Fuel to. Natural Uranium Fuel in a CANDU 6 Reactor Comparative Safety Evaluation of Thorium Fuel to Natural Uranium Fuel in a CANDU 6 Reactor COMPARATIVE SAFETY EVALUATION OF THORIUM FUEL TO NATURAL URANIUM FUEL IN A CANDU 6 REACTOR BY ZACHARY DEMERS,

More information

Lecture 18 Neutron Kinetics Equations

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

More information

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

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

More information

4 Nuclear Stability And Instability

4 Nuclear Stability And Instability 4 Nuclear Stability nd Instability Figure 4.1 Plot of N vs. Each black dot in Figure 4.1 represents a stable nuclide. Where more than one dot appears for a particular atomic number, those dots represent

More information

LECTURE 4: CORE DESIGN ANALYSIS

LECTURE 4: CORE DESIGN ANALYSIS Dr. Giovanni (John) Brenciagfia Lecture 4: Core Design Analysis LECTURE 4: CORE DESIGN ANALYSIS MODULE OBJECTIVES: At the end of this module, you will be able to specify the combination of numerical methods

More information

THORIUM SELF-SUFFICIENT FUEL CYCLE OF CANDU POWER REACTOR

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

More information

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

Radioactivity. Radioactivity

Radioactivity. Radioactivity The Law of Radioactive Decay. 72 The law of radioactive decay. It turns out that the probability per unit time for any radioactive nucleus to decay is a constant, called the decay constant, lambda, ".

More information

Physics Codes and Methods for CANDU Reactor

Physics Codes and Methods for CANDU Reactor Physics Codes and Methods for CANDU Reactor by Zhu XingGuan*, Cai Jianping* and Chow H.C.** *Shanghai Nuclear Engineering Research & Design Institute ** Atomic Energy of Canada Limited Abstract This paper

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

NEUTRONIC CALCULATION SYSTEM FOR CANDU CORE BASED ON TRANSPORT METHODS

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

More information

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

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

Process Modelling. Table of Contents

Process Modelling. Table of Contents Process Modelling 1 Process Modelling prepared by Wm. J. Garland, Professor, Department of Engineering Physics, McMaster University, Hamilton, Ontario, Canada More about this document Summary: The general

More information

3. Detector Systems. This chapter describes the CANDU detector systems.

3. Detector Systems. This chapter describes the CANDU detector systems. 3. Detector Systems This chapter describes the CANDU detector systems. 3.1 Zone-Control Detectors To vary the amount of water in the zone-control compartments, the Reactor Regulating System utilizes the

More information

CONTROL ROD WORTH EVALUATION OF TRIGA MARK II REACTOR

CONTROL ROD WORTH EVALUATION OF TRIGA MARK II REACTOR International Conference Nuclear Energy in Central Europe 2001 Hoteli Bernardin, Portorož, Slovenia, September 10-13, 2001 www: http://www.drustvo-js.si/port2001/ e-mail: PORT2001@ijs.si tel.:+ 386 1 588

More information

Nuclear Chemistry. The Nucleus. Isotopes. Slide 1 / 43. Slide 2 / 43. Slide 3 / 43

Nuclear Chemistry. The Nucleus. Isotopes. Slide 1 / 43. Slide 2 / 43. Slide 3 / 43 Slide 1 / 43 Nuclear Chemistry The Nucleus Slide 2 / 43 Remember that the nucleus is comprised of the two nucleons, protons and neutrons. The number of protons is the atomic number. The number of protons

More information

Recap from last time

Recap from last time Recap from last time Nuclear Decay Occurs. when a nucleus is unstable (lower open energy levels) An unstable nucleus metamorphoses ( decays ) into a more stable (more tightly bound) nucleus Difference

More information

Nuclear Theory - Course 127 FISSION

Nuclear Theory - Course 127 FISSION Nuclear Theory - Course 127 FISSION After having looked at neutron reactions in general, we shall use this lesson to describe the fission reaction and its products in some detail. The Fission Reaction

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

Introduction to Nuclear Reactor Kinetics

Introduction to Nuclear Reactor Kinetics ECOlE POLYTECHNIOUE Introduction to Nuclear Reactor Kinetics Course presented at Chulalongkorn University Bangkok, Thailand by Daniel Rozon, Ph.D., F.C.N.S. Institut de genie nucleaire Departement de genie

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

X. Assembling the Pieces

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

More information

PHYSICS A2 UNIT 2 SECTION 1: RADIOACTIVITY & NUCLEAR ENERGY

PHYSICS A2 UNIT 2 SECTION 1: RADIOACTIVITY & NUCLEAR ENERGY PHYSICS A2 UNIT 2 SECTION 1: RADIOACTIVITY & NUCLEAR ENERGY THE ATOMIC NUCLEUS / NUCLEAR RADIUS & DENSITY / PROPERTIES OF NUCLEAR RADIATION / INTENSITY & BACKGROUND RADIATION / EXPONENTIAL LAW OF DECAY

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

CHAPTER 5 Reactor Dynamics. Table of Contents

CHAPTER 5 Reactor Dynamics. Table of Contents 1 CHAPTER 5 Reactor Dynamics prepared by Eleodor Nichita, UOIT and Benjamin Rouben, 1 & 1 Consulting, Adjunct Proessor, McMaster & UOIT Summary: This chapter addresses the time-dependent behaviour o nuclear

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

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

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

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

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

Science 10: Radioactivity! Comparing Fission and Fusion Notes (Ch 11)

Science 10: Radioactivity! Comparing Fission and Fusion Notes (Ch 11) http://www.atomicarchive.com/movies/index.shtml Science 10: Radioactivity! Comparing Fission and Fusion Notes (Ch 11) Nuclear Reactions: an atom s nucleus changes by gaining or releasing particles or energy.

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

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

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

1.1 ALPHA DECAY 1.2 BETA MINUS DECAY 1.3 GAMMA EMISSION 1.4 ELECTRON CAPTURE/BETA PLUS DECAY 1.5 NEUTRON EMISSION 1.6 SPONTANEOUS FISSION

1.1 ALPHA DECAY 1.2 BETA MINUS DECAY 1.3 GAMMA EMISSION 1.4 ELECTRON CAPTURE/BETA PLUS DECAY 1.5 NEUTRON EMISSION 1.6 SPONTANEOUS FISSION Chapter NP-3 Nuclear Physics Decay Modes and Decay Rates TABLE OF CONTENTS INTRODUCTION OBJECTIVES 1.0 RADIOACTIVE DECAY 1.1 ALPHA DECAY 1.2 BETA MINUS DECAY 1.3 GAMMA EMISSION 1.4 ELECTRON CAPTURE/BETA

More information

Name Date Class NUCLEAR RADIATION. alpha particle beta particle gamma ray

Name Date Class NUCLEAR RADIATION. alpha particle beta particle gamma ray 25.1 NUCLEAR RADIATION Section Review Objectives Explain how an unstable nucleus releases energy Describe the three main types of nuclear radiation Vocabulary radioisotopes radioactivity radiation alpha

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

Binding Energy and Mass defect

Binding Energy and Mass defect Binding Energy and Mass defect Particle Relative Electric Charge Relative Mass Mass (kg) Charge (C) (u) Electron -1-1.60 x 10-19 5.485779 x 10-4 9.109390 x 10-31 Proton +1 +1.60 x 10-19 1.007276 1.672623

More information

Aluminum Half-Life Experiment

Aluminum Half-Life Experiment Aluminum Half-Life Experiment Definition of half-life (t ½ ): The half-life of any declining population is the time required for the population to decrease by a factor of 50%. Radioactive isotopes represent

More information

NATURAL CONVECTION HEAT TRANSFER CHARACTERISTICS OF KUR FUEL ASSEMBLY DURING LOSS OF COOLANT ACCIDENT

NATURAL CONVECTION HEAT TRANSFER CHARACTERISTICS OF KUR FUEL ASSEMBLY DURING LOSS OF COOLANT ACCIDENT NATURAL CONVECTION HEAT TRANSFER CHARACTERISTICS OF KUR FUEL ASSEMBLY DURING LOSS OF COOLANT ACCIDENT Ito D*, and Saito Y Research Reactor Institute Kyoto University 2-1010 Asashiro-nishi, Kumatori, Sennan,

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

"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

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

Energy. on this world and elsewhere. Visiting today: Prof. Paschke

Energy. on this world and elsewhere. Visiting today: Prof. Paschke Energy on this world and elsewhere Visiting today: Prof. Paschke Instructor: Gordon D. Cates Office: Physics 106a, Phone: (434) 924-4792 email: cates@virginia.edu Course web site available at www.phys.virginia.edu,

More information

Massachusetts Institute of Technology Physics Department

Massachusetts Institute of Technology Physics Department Massachusetts Institute of Technology Physics Department Physics 8.21 Fall 2011 Physics of Energy November 8, 2011 Quiz 2 Instructions Problem Points 1 50 2 25 3 25 (+ 20) Total 100 You must do problems

More information

Nuclear Physics Fundamentals and Application Prof. H.C. Verma Department of Physics Indian Institute of Technology, Kanpur

Nuclear Physics Fundamentals and Application Prof. H.C. Verma Department of Physics Indian Institute of Technology, Kanpur Nuclear Physics Fundamentals and Application Prof. H.C. Verma Department of Physics Indian Institute of Technology, Kanpur Lecture - 34 Nuclear fission of uranium So, we talked about fission reactions

More information

The 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 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 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

Information Nuclide = is an atomic species characterized by the specific constitution of its nucleus (protons and neutrons) Neutron

Information Nuclide = is an atomic species characterized by the specific constitution of its nucleus (protons and neutrons) Neutron NAME: DUE DATE: JULY nd AP Chemistry SUMMER REV: Balancing Nuclear Reactions Why? Nuclear reactions are going on all around us in the form of transmutation, fission and fusion. Using correctly balanced

More information

Nuclear 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 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 information

CHAPTER NEUTRON DETECTORS

CHAPTER 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

Lecture 7 Problem Set-2

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

More information

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

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

More information