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(a) Calculate the energy released in the neutron-induced fission (similar to the spontaneous fission in Example\(32.3\)) \(n{ + ^{238}}U{ \to ^{96}}Sr{ + ^{140}}Xe + 3n\), given \(m{(^{96}}Sr) = 95.921750{\rm{ }}u\) and \(m{(^{140}}Xe) = 139.92164{\rm{ }}u\).

(b) This result is about \(6{\rm{ }}MeV\) greater than the result for spontaneous fission. Why?

(c) Confirm that the total number of nucleons and total charge are conserved in this reaction.

Short Answer

Expert verified

(a) The energy released from the reaction\(n + {}^{238}U \to {}^{96}Sr + {}^{140}Xe + 3n\)is\(E = 177.08{\rm{ }}MeV\).

(b) In difference to the spontaneous fission we have by-products here which yields more energy.

(c) It is confirmed that the total number of nucleons and total charge are conserved in\(n + {}^{238}U \to {}^{96}Sr + {}^{140}Xe + 3n\)reaction.

Step by step solution

01

Concept Introduction

The power kept in the centre of an atom is known as nuclear energy. All stuff in the cosmos is made up of tiny particles called atoms. The centre of an atom's nucleus is typically where most of its mass is concentrated. Neutrons and protons are the two subatomic particles that make up the nucleus. Atomic bonds that hold them together carry a lot of energy.

02

Energy calculation

The energy release is happening due to the different total mass of nuclei before and after the nuclear reaction. Energydifference can be calculated by the free mass-energy formula –

\(E = \Delta m{c^2}\)

To get these mass differences take parent nuclei and subtract from them daughter nuclei and masses of all otherby-products of the nuclear reaction. Since all atomic masses will be expressed with the unified atomic unit, remember how to convert it to\(eV\)–

\(lu = \frac{{931.5{\rm{ }}MeV}}{{{c^2}}}\)

Now analyse the reaction –

\(n + {}^{238}U \to {}^{96}Sr + {}^{140}Xe + 3n\)

Looking in the Appendix for the atomic masses the following is obtained–

\(\begin{array}{c}neutron = 1.008665{\rm{ }}u\\^{238}U = 238.05078{\rm{ }}u\\^{96}Sr = 95.92175{\rm{ }}u{\rm{ }}\\^{140}Xe = 139.92164{\rm{ }}u\end{array}\)

Expression for mass difference will be –

\(\Delta m = m(n) + m{(^{238}}U) - \{ m{(^{96}}Sr) + m{(^{140}}Xe) - 3m(n)\} \)

Plugging in the values –

\(\begin{array}{c}\Delta m = 1.008665{\rm{ }}u + 238.05078{\rm{ }}u - 95.92175{\rm{ }}u{\rm{ }} - 139.92164{\rm{ }}u - 31.008645{\rm{ }}u\\\Delta m = 0.1901{\rm{ }}u\end{array}\)

So, from the energy relation it is obtained that –

\(\begin{array}{c}E &= \Delta m{c^2}\\ &= 0.1901 \cdot \frac{{931.5MeV}}{{{c^2}}} \cdot {c^2}\\E &= 177.08{\rm{ }}MeV\end{array}\)

Therefore, the energy value for the reaction is obtained as \(E = 177.08{\rm{ }}MeV\).

03

Greater Result

In the spontaneous fission there are notby-products from stable to unstable uranium, meaning\(^{238}U\)goes directly to the\(^{239}U\). Because of the by-products and elements in

between this process is more energy-rich.

Therefore, because of by-products the result obtained is greater.

04

Number of nucleons and charge

Regarding the conservation of nucleons and charge, check the reaction –

\(n + {}^{238}U \to {}^{96}Sr + {}^{140}Xe + 3n\)

To be conserved we need a total charge on the left and right sides to be the same, as the total number of nucleons on the left and rightsides to be the same.

For the left side –

Nucleons

Charges

\(n\)

\(1\)

\(0\)

\({}^{238}U\)

\(238\)

\(92\)

And for the right side –

Nucleons

Charges

\(3n\)

\(3\)

\(0\)

\({}^{96}Sr\)

\(96\)

\(38\)

\({}^{140}Xe\)

\(140\)

\(54\)

Regarding the number of nucleons on the left side we have\(1 + 238 = 239\), and on the right side, there is\(3 + 96 + 140 = 239\), which isconserved.

When it comes to the conservation of the charge, on the left we got\(92\)from uranium itself, and on the right side, we got\(38 + 54 = 92\)from\(Sr\)and\(Xe\). The number is equal so the charge is also conserved.

Therefore, all the quantities are conserved.

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Most popular questions from this chapter

The power output of the Sun is \(4 \times {10^{26}}{\rm{ }}W\).

(a) If \(90\% \) of this is supplied by the proton-proton cycle, how many protons are consumed per second?

(b) How many neutrinos per second should there be per square meter at the Earth from this process? This huge number is indicative of how rarely a neutrino interacts, since large detectors observe very few per day.

The naturally occurring radioactive isotope \(^{{\rm{232}}}{\rm{Th}}\) does not make good fission fuel, because it has an even number of neutrons; however, it can be bred into a suitable fuel (much as \(^{{\rm{238}}}{\rm{U}}\) is bred into\(^{239}P\)).

(a) What are Z and N for\(^{{\rm{232}}}{\rm{Th}}\)?

(b) Write the reaction equation for neutron captured by \(^{{\rm{232}}}{\rm{Th}}\) and identify the nuclide \(^AX\)produced in\(n{ + ^{232}}Th{ \to ^A}X + \gamma \).

(c) The product nucleus \({\beta ^ - }\)decays, as does its daughter. Write the decay equations for each, and identify the final nucleus.

(d) Confirm that the final nucleus has an odd number of neutrons, making it a better fission fuel.

(e) Look up the half-life of the final nucleus to see if it lives long enough to be a useful fuel.

(a) Neutron activation of sodium, which is \({\rm{100\% }}\,{\,^{{\rm{23}}}}{\rm{Na}}\), produces\(^{{\rm{24}}}{\rm{Na}}\), which is used in some heart scans, as seen in Table 32.1. The equation for the reaction is \(^{23}Na + n{ \to ^{24}}Na + \gamma \). Find its energy output, given the mass of \(^{{\rm{24}}}{\rm{Na}}\) is \(23.990962\,u\).

(b) What mass of \(^{{\rm{24}}}{\rm{Na}}\) produces the needed \(5.0\)-mCi activity, given its half-life is \(15.0\,\;h\) ?

Find the radiation dose in \({\bf{Gy}}\) for: (a) A \(10 - mSv\)fluoroscopic x-ray series.

(b) \(50\,{\rm{mSv}}\) of skin exposure by an \(\alpha \) emitter.

(c) \(160\,{\rm{mSv}}\)of \({\beta ^ - }\)and \(\gamma \)rays from the \(^{40}\;{\rm{K}}\) in your body.

How does the lithium deuteride in the thermonuclear bomb shown in Figure \({\rm{32}}{\rm{.33}}\) supply tritium (\({}^3H\)) as well as deuterium (\({}^2H\))?

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