nuclear fission

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1 Nuclear Fission Nuclear Reactors, BAU, 1 st Semester, 2007-2008 (Saed Dababneh). • Thermal neutron fission of 235 U forms compound nucleus that splits up in more than 40 different ways, yielding over 80 primary fission fragments (products). 235 92 U + 1 0 n ► 90 37 Rb + 144 55 Cs + 2 1 0 n 235 92 U + 1 0 n ► 87 35 Br + 146 57 La + 3 1 0 n 235 92 U + 1 0 n ► 72 30 Zn + 160 62 Sm + 4 1 0 n • The fission yield is defined as the proportion (percentage) of the total nuclear fissions that form products of a given mass number. Revisit thermal and look for fast. 1 Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

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Nuclear Fission. Thermal neutron fission of 235 U forms compound nucleus that splits up in more than 40 different ways, yielding over 80 primary fission fragments (products). 235 92 U + 1 0 n ► 90 37 Rb + 144 55 Cs + 2 1 0 n 235 92 U + 1 0 n ► 87 35 Br + 146 57 La + 3 1 0 n - PowerPoint PPT Presentation

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Page 1: Nuclear Fission

1

Nuclear Fission

Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

• Thermal neutron fission of 235U forms compound nucleus that splits up in more than 40 different ways, yielding over 80 primary fission fragments (products).

23592U + 1

0n ► 9037Rb + 144

55Cs + 210n

23592U + 1

0n ► 8735Br + 146

57La + 310n

23592U + 1

0n ► 7230Zn + 160

62Sm + 410n

• The fission yield is defined as the proportion (percentage) of the total nuclear fissions that form products of a given mass number. Revisit thermal and look for fast.

1Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 2: Nuclear Fission

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

2

Nuclear Fission

Asymmetry

Asymmetry

• Remember neutron excess.• (A,Z) (A,Z+1) or (A-1,Z).

Only left side of the

mass parabola.

Page 3: Nuclear Fission

3

Nuclear Fission

• 235U + n 93Rb + 141Cs + 2n• Q = ????• What if other fragments?• Different number of neutrons.• Take 200 MeV as a representative value.

66 MeV 98 MeV

miscalibrated

Heavyfragments

Lightfragments

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

165 MeV average kinetic energy carried

by fission fragments per

fission.

Page 4: Nuclear Fission

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

4

Nuclear Fission• neutrons emitted per fission.• depends on fissioning nuclide and on neutron energy inducing fission.

Page 5: Nuclear Fission

5

Nuclear Fission• Mean neutron energy 2 MeV.• 2.4 neutrons per fission (average) 5 MeV average kinetic energy carried by prompt neutrons per fission.

• Show that the average momentum carried by a neutron is only 1.5 % that carried by a fragment. • Thus neglecting neutron momenta, show that the ratio between kinetic energies of the two fragments is the inverse of the ratio of their masses.

1

2

2

1

m

m

E

E

140

95

98

66

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 6: Nuclear Fission

6

Nuclear Fission

Distribution of fission energy

Krane sums

them up as

decays.Lost … !

Enge

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 7: Nuclear Fission

7

Segrè

Lost … !

Nuclear Fission

• How much is recoverable?How much is recoverable?• What about capture gammas? What about capture gammas? (produced by (produced by -1 neutrons)-1 neutrons)

• Why c < (a+b) ?Why c < (a+b) ?

Distribution of fission energy

abc

Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 8: Nuclear Fission

8Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

• and emissions from radioactive fission products carry part of the fission energy, even after shut down. • On approaching end of the chain, the decay energy decreases and half-life increases. Long-lived isotopes constitute the main hazard.• Can interfere with fission process in the fuel. Example?Example? (poisoning).(poisoning).• Important for research.• -decay favors high energy ~20 MeV compared to ~6 MeV for .

• Only ~ 8 MeV from -decay appears as heat. Why?Why?

Nuclear Fission

Page 9: Nuclear Fission

9

Nuclear Fission

Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

A, Zi

A, Z-1k

A-1, Zj

A, Z+1A+1, Z

-

-

(n,)

(n,)

dNi/dt = Formation Rate - Destruction rate - Decay Rate

iiiikkjjffii NNNNN

dt

dN

f

Ni saturates and is higher with higher neutron flux, larger “fission yield” and longer half-live.

9Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 10: Nuclear Fission

Investigate both and giving full description for the buildup and decay of fission fragment i.

10

Nuclear Fission

Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

iikki NN

dt

dN

iikk NN

• Shutdown

iikk NN HW 8HW 8

HW 7HW 7

Investigate the activity, decay and gamma energies of fission products as a function of time. Comment on consequences (e.g. rod cooling).

10Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 11: Nuclear Fission

11Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

sMeVTttxtP /)(101.4)( 2.02.011 per watt of original operating power.T = time of operation.

Nuclear Fission

Fission product activity after

reactor shutdown?

11Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 12: Nuclear Fission

Nuclear Fission

• The fission gamma radiation Prompt within 0.1 s and with average energy of 0.9 MeV. delayed gammas.

• Investigate how prompt Investigate how prompt gammas interact with gammas interact with water, uranium and lead.water, uranium and lead.

12Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

HW 9HW 9

12Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 13: Nuclear Fission

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

13

Nuclear Fission

EeE E 29.2sinh453.0)( 036.1HW 10HW 10

The experimental spectrum of prompt neutrons is fitted by the above equation. Calculate the mean and the most probable neutron energies.

Page 14: Nuclear Fission

14Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

• Recoverable energy release 200 MeV per 235U fission.• Fission rate = 2.7x1021 P fissions per day. P in MW.• 3.12x1016 fissions per second per MW, or 1.2x10-5 gram of 235U per second per MW (thermal).• Burnup rateBurnup rate: 1.05 P g/day. P in MW. • The fissioning of 1.05 g of 235U yields 1 MWd of energy. • Specific Burnup Specific Burnup = 1 MWd / 1.05 g 950000 MWd/t (pure (pure 235235U !!).U !!).• Fractional Burnup Fractional Burnup = ???• Thermal reactor loaded with 98 metric tons of UO2, 3% enriched, operates at 3300 MWt for 750 days.• 86.4 t U. Specific burnup 28650 MWd/t. • Not all fissions from 235U.• Fast fission of 238U.• 238U converted to plutonium more fission.

Nuclear Fission

Work it out, NOW!

Work it out, NOW!

Actually much less.Actually much less.

Page 15: Nuclear Fission

Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

15

Nuclear Fission

•Two neutrinos are expected immediately from the decay of the two fission products, what is the minimum flux of neutrinos expected at 1 km from the reactor.

)(

)()(

E

EE

f

• Capture-to-fission ratio:

• Consumption rateConsumption rate: 1.05(1+) P g/day.

• Read all relevant material in Lamarsh Read all relevant material in Lamarsh Ch. 4. We will come back to this later.Ch. 4. We will come back to this later.

4.8x1012 m-2s-1

Page 16: Nuclear Fission

16Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

Nuclear Fission

• 3.1x1010 fissions per second per W.• In thermal reactor, majority of fissions occur in thermal energy region, and are maximum.• Total fission rate in a thermal reactor of volume V

• Thermal reactor powerThermal reactor power (quick calculation) (quick calculation)

fV

10101.3 x

VP f

th

16Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).

Page 17: Nuclear Fission

Nuclear Fission

• It is necessary to evaluate the potential hazards associated with an accidental release of fission products into the environment.

• It is required to determine a proper cooling time of the spent fuel (before it becomes ready for reprocessing) that depends on the decay times of fission products.

• It is necessary to estimate the rate at which the heat is released as a result of radioactive decay of the fission products after the shut down of a reactor.

• The poisoning is needed to be calculated (the parasitic capture of neutrons by fission products that accumulate during the reactor operation).

17Nuclear Reactors, BAU, 1st Semester, 2007-2008 (Saed Dababneh).

17Nuclear Reactors, BAU, 1st Semester, 2008-2009 (Saed Dababneh).