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Phase diagram of water

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B/A<br />

Fusion<br />

Binding Energy <strong>of</strong> Nuclei<br />

Fission<br />

Mass Number A<br />

MeV<br />

Above mass ~20 approximately constant binding energy per nucleon<br />

However: more stable nuclei can be formed either by:<br />

i) Fusion (combining 2 nuclei with low mass number A)<br />

ii) Fission (breakup <strong>of</strong> large A nucleus into lower A fragments plus<br />

release <strong>of</strong> neutrons)<br />

8<br />

6<br />

4<br />

2<br />

0<br />

In fission<br />

A 1 → A 2 + A 3 + neutrons,<br />

where A 2 and A 3 are the final<br />

stable nuclei, the total energy<br />

release E R is approximately<br />

E R = A 2 {b(A 2 ) − b(A 1 )} +<br />

A 3 {b(A 3 ) − b(A 1 )}.<br />

Basic Ideas : Fission Reactors<br />

141<br />

Ba 56<br />

n<br />

n<br />

235 236<br />

U U n<br />

92 92<br />

n<br />

neutron<br />

92<br />

Kr<br />

absorption<br />

36<br />

fission<br />

n + 235 U 92 141 Ba 56 + 92 Kr 36 + 3n<br />

Change in mass, δm = 3.6 10 −28 kg<br />

Energy released, E = (δm)c 2<br />

= (3 10 8 ) 2 3.6 10 −28<br />

= 3.2 10 −11 J<br />

⇒ chain reaction<br />

cf chemical combustion<br />

C + O 2 CO 2 E = 7 10 −19 J<br />

Energy release from 1 uranium nucleus = 5 10 7 carbon atoms<br />

1 tonne <strong>of</strong> 235 U = 2.7 10 6 tonnes <strong>of</strong> coal<br />

U is 0.7% 235 U so 1 tonne U ≡ 20,000 tonnes <strong>of</strong> coal<br />

Naturally-occurring uranium consists <strong>of</strong><br />

• fissile isotope 235 U<br />

• stable isotope 238 U }ratio = 1/138 ~ 0.7%<br />

In a reactor, neutrons are lost by :<br />

1) absorption by 238 U 239 U 239 Pu<br />

2) absorption by 235 U 236 U (18% for thermal n)<br />

3) absorption by moderator<br />

4) absorption by reactor structure<br />

5) escape from reactor core<br />

Not enough n to continue chain reaction with H 2 O moderation<br />

enrichment necessary to increase ratio 235 U/ 238 U 3%<br />

Note: the naturally-occurring ratio was higher in the past<br />

%<br />

Oklo ‘reactor’ (Gabon)<br />

3<br />

0.7<br />

−2.10 9<br />

−10 9<br />

0<br />

years<br />

β<br />

nb t 1/2 <strong>of</strong><br />

235<br />

U = 7.1 10 8 years<br />

cf t 1/2 <strong>of</strong><br />

238<br />

U = 3 10 9 years<br />

Fuel Enrichment<br />

Enrichment is process <strong>of</strong> increasing proportion <strong>of</strong> fissionable nuclei<br />

in natural uranium (0.7% 235 U)<br />

Methods <strong>of</strong> enrichment<br />

1 Electromagnetic Separation<br />

accelerating<br />

electrodes<br />

B<br />

mv 2 /r = qBv r = mv/qB<br />

vacuum chamber<br />

heavy isotope<br />

light isotope<br />

Used for Manhattan project (1g/day) and by Iraq before Gulf War

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