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1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain...

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1 Controlled Fission 235 U + n X + Y + (~2.4)n • Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. • Ratio of number of “neutrons” (fissions) in one generation to the preceding k (neutron reproduction or multiplication factor). k 1 Chain reaction. k < 1 subcritical. k = 1 critical system. k > 1 supercritical. For steady release of energy (steady- state operation) we need k =1. Fast second generation neutro Infinite medium (ignoring leakage at the surface). Chain reacting pile Chain reacting pile Nuclear Reactors, BAU, 1 st Semester, 2007-2008 (Saed Dababneh).
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Page 1: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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Controlled Fission

• 235U + n X + Y + (~2.4)n• Moderation of second generation neutrons Chain reaction.• Water, D2O or graphite moderator.• Ratio of number of “neutrons” (fissions) in one generation to the preceding k (neutron reproduction or multiplication factor).

• k 1 Chain reaction.• k < 1 subcritical.• k = 1 critical system.• k > 1 supercritical.For steady release of energy (steady-state operation) we need k =1.

Fast second generation neutrons

Infinite medium (ignoring leakage at the surface).

Chain reacting pileChain reacting pile

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

Page 2: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

Controlled Fission• Average number of all neutrons released per fission

(for thermal neutrons, 0.0253 eV).• 233U : 2.492• 235U : 2.418• 239Pu : 2.871• 241Pu : 2.927

• Reactor is critical (k = 1): rate of neutrons produced by fission = rate of neutrons absorbed absorbed + leaked.Size and composition of the reactor.

Page 3: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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

3

Probability for a thermal neutron to cause fission on 235U is

Controlled Fission

235U thermal cross sectionsfission 584 b.scattering 9 b.radiative capture 97 b.

1

1

f

f

If each fission produces an average of neutrons, then the mean number of fission neutrons produced per thermal neutron =

1f

f

a

f <

Page 4: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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Controlled Fission235U

238U

• Assume Assume natural natural uranium:uranium:99.2745% 238U, 0.7200% 235U.

• f / N = (0.992745)(0) + (0.0072)(584)

= 4.20 b.• / N = (0.992745)(2.75) +

(0.0072)(97) = 3.43 b.

Thermal f = 0 b 584 bThermal = 2.75 b 97 b

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

N

NN

yyxx

yyxxyx

)(

24 R

24 R

Using the experimental elastic scattering data the radius of the nucleus can be estimated.

Doppler effect?Doppler effect?

Page 5: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

Moderation (to compare x-section)

1H

(n,) (n,)

(n,n)(n,n)2H

• Resonances?

Page 6: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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• Probability for a thermal neutron to cause fission in natural natural uraniumuranium

• If each fission produces an average of = 2.4 neutrons, then the mean number of fission neutrons produced per thermal neutron = = 2.4 x 0.55 1.3• This is close to 1. If neutrons are still to be lost, there is a danger of losing criticality. (Heavy water?).• For enriched uraniumenriched uranium (235U = 3%) = ????? (> 1.3). (Light water?).• In this case is further from 1 and allowing for more neutrons to be lost while maintaining criticality.

55.043.320.4

20.4

Controlled Fission

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

Page 7: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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

7

Controlled Fission

i

fa

ii )()(1 • Verify

• Comment on the calculation for thermal neutrons and a mixture of fissile and non-fissile materials, giving an example.• Comment for fast neutrons and a mixture of fissionable materials, giving an example.

HW 11HW 11

Page 8: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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Converters: Convert non-thermally-fissionable material to a thermally-fissionable material.

_2393.2

_239min23239238

Pu

NpUnU

d

f,th = 742 b

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

_23327

_233min22233232

U

PaThnTh

d

f,th = 530 b

Conversion and Breeding

Page 9: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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• If = 2 Conversion and fission.• If > 2 Breeder reactor.• 239Pu: Thermal neutrons ( = 2.1) hard for breeding.

Fast neutrons ( = 3) possible breeding fast breeder reactors.

After sufficient time of breeding, fissile material can be easily (chemically) separated from fertile material.Compare to separating 235U from 238U.

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

Conversion and Breeding

Delicate neutron economy…!

Page 10: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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Controlled Fission• N thermalthermal neutrons in one generation have produced have produced so far so far NN fast neutrons.fast neutrons.• Some of these fast neutrons can cause 238U fission more fast neutrons fast fission factor fast fission factor = (= 1.03 for natural uranium).• Now we have Now we have NN fast neutrons. fast neutrons.• We need to moderate these fast neutrons use graphite for 2 MeV neutrons we need ??? collisions. How many for 1 MeV neutrons?• The neutron will pass through the 10 - 100 eV region during the moderation process. This energy region has many strongstrong 238U capture resonances (up to ????? b) Can not mix uranium and graphite as powders.• In graphite, an average distance of 19 cm is needed for thermalization the resonance escape probability resonance escape probability p ( 0.9).Nuclear Reactors, BAU, 1st Semester, 2007-2008

(Saed Dababneh).

Page 11: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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Controlled Fission• Now we have Now we have ppN N thermal neutrons.thermal neutrons.• Graphite must not be too large to capture thermal neutrons; when thermalized, neutrons should have reached the fuel.• Graphite thermal cross section = 0.0034 b, but there is a lot of it present.• Capture can also occur in the material encapsulating the fuel elements.• The thermal utilization factor thermal utilization factor f ( 0.9) gives the fraction of thermal neutrons that are actually available for the fuel.• Now we have Now we have fpfpNN thermal neutrons thermal neutrons, could be > or < N thus determining the criticality of the reactor.

k = fp The four-factor formula.The four-factor formula.

k = fp(1-lfast)(1-lthermal)Fractions lost at surfaceNuclear Reactors, BAU, 1st Semester, 2007-2008

(Saed Dababneh).

Page 12: 1 Controlled Fission 235 U + n X + Y + (~ 2.4) n Moderation of second generation neutrons Chain reaction. Water, D 2 O or graphite moderator. Ratio of.

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x 1.03x 1.03Fast fission Fast fission factor “factor “””

x 0.9x 0.9Resonance Resonance

escape escape probability ”p”probability ”p”

x 0.9x 0.9Thermal Thermal

utilization utilization factor “f”factor “f”

x

What is:• Migration length?• Critical size?How does the geometry affect the reproduction factor?

Neutron reproduction

factork = 1.000

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


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