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Decay chains

relation ofA and  B ?

1

1/2, 1/2,

X Y

stable

X Y

X Y Z

T T

 

 

 

  

,0  Y e X t e Y t

Y Y Y X

Y X

A N A

(2)

90 90 90

28a 64h

Sr 

Y 

Zr

1 2,X



1 2,Y

T T

T

1/2,X

= 8·10

7

h

T

1/2,Y

=0,8h

2

(3)

222Rn

86 234Th

90 234Pa

234U

92

230Th

90

226Ra

88 22286Rn

238U

92

214Po

84 21483Bi 21482Pb 21884Po 22286Rn

radonnak a talajban maradó

része

rések, ahol a radon egy része kijut a talajból a légkörbe további hosszú felezési

idejű leányelemek

AEROSZOLOK

FÖLDFELSZíN

ESŐCSEPPEK

csapadék ülepedés

légáramlás

3

226 222

86 82

88

Ra 

1620a

Rn 

3,83 d

 ... Pb

aerosol raindrops

Surface of the Earth

Further long T1/2 daughters

precipitation sedimentation

air current

cracks where Rn can escape to the atmosphere

Rn remaining underground

(4)

4

210

Po is an -emitter, that has a half-life of 138.4 days, E

= 5.3 MeV

When former Russian spy Alexander Litvinenko died from polonium-210 poisoning several years ago in London,

it triggered a murder investigation that developed like a thriller.

Po-210 generate much heat as the atoms decay - it was used in Russian lunar landers to keep the craft's

instruments warm at night.

.

(5)

Interaction of the radiation with the matter

5

(6)

Partners

1. Electromagnetic field 2. Electron

3. Field of the nucleus 4. Nucleus

A) Absorption I Ekin, E*

C) Incoherent scattering (also exchange of E) I, E

elastic (no excitation) Ekin

inelastic Ekin, E*

B) Coherent scattering (only the direction I - is altered))

Effect on

Mechanism radiation matter

Particles/photons

I. II. III.

a b

p e+ n

e- X

6

(7)

1. Ionizing radiations

7

(8)

The first step of the ionizing radiation in the matter:

1. Neutral excitation

A + radiation A* + radiation’

2. External ionization

A + radiation A+ + e- + radiation’

3. Internal ionization

A + radiation A*+ + e- + radiation’

A*+ A+ + Xchar A*+ A2+ + e-Auger 4. Bremsstrahlung (breaking radiation)

A + radiation A + Xb + radiation

F

UNDAMETALS OF DETECTION

8

(9)

Quantitative description of the interaction

    nx

A

 dn   (E)n 

A

dx

 

0 (E) Ax

n n e

0 x

I I e

linear absorption coefficient

9

0 0 0

m

x d

I I e x I e I e

  

   

mass absorption

coefficient cross section

n

I t

(10)

-radiation

With electrons: incoherent scattering ionisation and excitation (50-50 %)

E and direction of the alpha particles is modified With the nucleus: Rutherford-scattering

nuclear reaction (see later)

! Bremsstrahlung (continuous energy gamma radiation)!

Intensity

10

Heavy, charged, high energy

distance in air

(11)

-radiation

With electron: incoherent scattering ionisation (external and internal) excitation

E and the direction of the radiation changes With the field of the nucleus: incoherent scattering

! Bremsstrahlung !

 

 

  

 

 

 

r

ion

dE

dx EZ

dE 800 dx

m

d x

0 0

I  I e   I e 

Linear/mass absorption coefficient11 Monoenerg

n et

tro ic elec

-rad

iation

Thickness

small, charged, limited energy

(12)

12

air

Linear energy transfer (LET)

2

dE / dx 1/ v

(13)

13

Calculate the activity of 1 kg KCl. 0.012 % of the K atoms is radioactive 40K. The half life of 40K is 1.13109 years.

We prepared a 35S labelled protein at 12:00, 10 September 2014. The half life of the pure - emitter is 88 days. This

sample was measured at noon on 26 September and the intensity was found 7000 imp/s. The overall effieciency of the

measurement was 22 %. Calculate the activity of the sample in the time of synthesis.

The linear absorption coefficient of gamma radiation of 660 keV in aluminum is 3,4 cm-1. Calculate the half thickness. How

efficiently will attenuate this radiation an 10 cm aluminum wall ?

(14)

1. Compton-scattering Elastic collision of the photon with an electron

-radiation

E’ EC

E

where 

C

= 

s

+ 

a

14

electromagnetic radiation

C A A

C ,m C C

N Z A

 

     

 

(15)

2. Photoelectric effect

n(E)=4 - 5

15

(16)

3. Pair production

16

(17)

17

( )

0 0

C f p

d

II e dI e

pair Compton

Photo Photo Pair

Germanium

(18)

2. Nuclear reactions

18

(19)

10B +  10B + 

14N* 13C +p

12C + d  13N+n

Transition state

1. (n,)

(n,f) 233U, 235U, 239Pu, 241Pu

10B(n,)

6Li(n,)

2. (,n)

(n,2n) (n,) (p, ) (d, )

Cross section (~probability)

Tunnel effect 19 Conventional equation

(20)

* * a

dN N N

dt     

 

* *

1 exp

NN

    t

 

1 exp

AA

    t

Kinetics of the nuclear reactions

*

A

  N

 

a

N   

 

 

      '

1 exp exp

h

A N

A t t

activation decay 20

meas.

end of activation

(21)

21

We intend to obtain 65Ni with neutron irradiation. Therefore, we

expose 1 g of Ni (with a 64Ni content of 91 %) to neutrons with a flux

=1012 1/cm2s. Thre cross section of the

64Ni(n,)65Ni

reaction is 1.55·10-28 m2. The half-life of 65Ni is 2.52 h.

i) How long should the irradtiation last if we want to reach 80 % of the saturation activity?

ii) Estimate the ratio of the 64Ni/65Ni isotopes in the sample after being „cooled” for the same period as the activation lasted.

(22)

- elastic scattering

- inelastic scattering

Excited nucleus, h

- neutron capture

(absorption): (n,?)

Interaction of neutrons with the matter

22

relatively heavy, no charge, energy ?

(23)

1. Slow

a) cold E  0.025 eV

b) thermal 0.025 eV  E  0.44 eV c) resonance 0.44 eV  E  1000 eV

2. Medium 1 keV  E  500 keV

3. Fast 0.5 MeV  E  10 MeV

4. High energy 10 MeV  E  50 MeV

5. Super fast 50 MeV  E

Due to the strong E dependence,

23

(24)

113

Cd(n,)

114

Cd  =6,31·10

-24

m

2

     

10 B n , 7 Li 3 10 25 m 2

135Xe(n,  )136Xe   2,7 10  22 m 2 , 149Sm(n,  )150Sm   6,6 10  24 m 2 ,

157Gd(n,  )158Gd   4,6 10  23 m 2 ,

n ,  

n ,

Examples of practical relevance

24

(25)

25

n f ,  fission

(26)

Fission ( n,f )

 

 

 

236U

 

235

U n 3 n

90

Kr+

143

Ba +200 MeV

50 ways, 300 isotopes 35 elements





90 90

33 s 2,7 min

Kr

Rb

90 90 90

28a 64h

Sr 

Y 

Zr

26

(27)

kinetic energy of fission products:  160 MeV kinetic energy of the neutrons:  5 MeV

energy of the -rays:  5 MeV

energy of the secondary radioactive decay:  20 MeV energy released at neutron capture:  10 MeV

Distribution 200 MeV

Self-sustaining chain reaction: control

27

(28)

Nuclear reactor

28

Fuel

Moderator

Cooling system Control

Hivatkozások

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