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The annual radiation dose from \(^{14}{\rm{C}}\)in our bodies is \(0.01\,{\rm{mSv}}/{\rm{y}}\). Each \(^{14}{\rm{C}}\) decay emits a \({\beta ^ - }\) averaging \(0.0750\,{\rm{MeV}}\). Taking the fraction of \(^{14}{\rm{C}}\)to be \(1.3 \times {10^{ - 12}}\;{\rm{N}}\)of normal \(^{12}{\rm{C}}\), and assuming the body is \(13\% \) carbon, estimate the fraction of the decay energy absorbed. (The rest escapes, exposing those close to you.)

Short Answer

Expert verified

The estimated fraction of energy decay absorbed for \(^3{\rm{He}}{ + ^3}{\rm{He}}{ \to ^4}{\rm{He}}{ + ^1}{\rm{H}}{ + ^1}{\rm{H}}\) is \(x = 0.95218 = 95\% \).

Step by step solution

01

Concept of radiation

Energy is released spontaneously as energetic subatomic particles or electromagnetic waves from radioactive atoms. Radiation is the term for the emissions.

A radiation dose is a measurement of how much energy a source of radiation deposits into a material.

02

Step 2: Calculate the mass

In this problem we are to estimate the fraction of energy decay absorbed for\(^3{\rm{He}}{ + ^3}{\rm{He}}{ \to ^4}{\rm{He}}{ + ^1}{\rm{H}}{ + ^1}{\rm{H}}.\)

To calculate the mass, first we should remind the definition of the activity:\(R = \frac{{0.693N}}{{{t_{1/2}}}}\)

Where,\(N\) is the number of the atoms, which can also be calculated via molar mass and Avogadro number:\(N = \left( {\frac{m}{M}} \right){N_A}\)
Joule of energy is delivered to each kilogram of absorbing material:\(1\,\frac{{{\rm{J/kg}}}}{{{\rm{Gy}}}} = 1\,\,{\rm{rad}}\)

And also:\({\rm{ }}Sv{\rm{ }} = {\rm{ }}Gy \times RBE,{\rm{ }}and{\rm{ }}1{\rm{ }}Sv{\rm{ }} = 100{\rm{ }}rem{\rm{ }}\)

So to get energy from this radioactive decay of we use the following relation:

\(E = Rt\Delta E\)

Where\(t\) is the time in which dose was received and\(\Delta E\)is the energy per decay. We put in the relation for activity and we get:\(E = \frac{{0.693N}}{{{t_{1/2}}}}t\Delta E\)

Because we are estimating only a fraction of energy and not whole (because the rest escapes), we can note that fraction of the energy by\(x\):\(E = \frac{{0.693N}}{{{t_{1/2}}}}t\Delta Ex\)

And since we do not know the number of particles we can use the formula with the molar mass and Avogadro number, so we write: \(E = \frac{{0.693\left( {\frac{m}{M}} \right){N_A}}}{{{t_{1/2}}}}t\Delta {E_x}\)

03

Step 3: Calculate the received energy

Consider the given information.

We need to take into account the received dose. 50 Kg is exposed into ionizing radiation over the body she absorbs 1.00J her received dose is:\((1.00\;{\rm{J}})/(50.0\;{\rm{kg}}) = 0.0200\;{\rm{J}}/{\rm{kg}} = 2.00\,{\rm{rad}}\)

So we know that expression to calculate the energy of radiation is:\(E = {\rm{ dose}} \times m\)

And this is the dose in Joules, to get it in rem, we remember that\(1\,rad\, = \,0.01\;J/kg,\,\,50\):

\(E = {\rm{ dose}} \times m \times 0.01\;{\rm{J}}/{\rm{kg}}\)

And here\(m\)is exactly the mass of the radioactive element that is producing the radiation dose.

For the naturally occurring\(^{14}{\rm{C}}\) we would like to know the radiation dose in\({\rm{J}}/{\rm{kg}}\), so we must include the\(RBE\)factor, which is for the\(\beta \)rays exactly\(1\). So the does will be:\({\rm{ dose rad = }}\frac{{{\rm{ dose rem }}}}{{{\rm{RBE}}}}\)

Putting in the values we have (remembering that (\(1\;{\rm{Sv}} - 100\)rem):

\({\rm{ }}dose{\rm{ }}rad{\rm{ }} = \frac{{0.01m\,\,rem/y}}{1}\)

To get the units we want we have:\({\rm{ }}dose{\rm{ }}rad = \frac{{1 \times {{10}^{ - 3}}1/y}}{1} \times 0.01\frac{J}{{kg}}\)

So the received does in \({\rm{J}}/{\rm{kg}}\)in one year will be:\({\rm{ }}dose{\rm{ }}rad{\rm{ }} = \frac{{1 \times {{10}^{ - 5}}}}{1}\frac{J}{{kgy}}\).

04

Step 4: Estimate the fraction of energy decay

Let us calculate fraction of energy decay.

We have already written the relation that is connecting the radiation dose and delivered energy to the body:

\(E = dose \cdot {m_C}\)

We put in expression for the energy here (and we are taking only 13% of the energy so we write:

\(\frac{{0.693\left( {\frac{m}{M}} \right){N_A}}}{{{t_{1/2}}}}t\Delta Ex = {\rm{ dose}} \times {m_C}\)

And expressing only the mass of our radioactive element we have:

\(x = \frac{{{\rm{ dose }} \cdot {m_C} \cdot {t_{1/2}} \cdot M}}{{t \cdot \Delta E \cdot {N_A} \cdot 0.693 \cdot m}}\)

We need to take into account we are taking only a fraction of carbon\(14,1.3 \times {10^{ - 12}}\;{\rm{N}}\), which is\(13\% \)equals to\(1.69 \times {10^{ - 13}}\), so we got:\(x = \frac{{{\rm{ dose}} \times {m_C} \times {t_{1/2}} \times M}}{{t \times \Delta E \times {N_A} \times 0.693 \times 1.69 \times {{10}^{ - 13}}}}\)

The molar mass is\(14.003\)as found in the Appendix. We also convert\(0.075{\rm{MeV}}\)to Joules (given\(1{\rm{eV}} = 1.6 \times {10^{ - 19}}\;{\rm{J}}\)) which is\(1.2 \times {10^{ - 14}}\)Joules, while also seen from the Appendix half-life is\(1.28 \times {10^9}{\rm{y}}\)\(1.28 \times {10^9}{\rm{y}}\). Now we have all the information to calculate the mass:

\(x = \frac{{1 \times {{10}^{ - 5}}\frac{{\rm{J}}}{{kgy}} \times 5730\,{\rm{y}} \times 0.014003\,\;{\rm{kg}}/{\rm{mol}}}}{{1\,{\rm{y}} \times 1.2 \times {{10}^{ - 14}}\;{\rm{J}} \times 6.022 \times {{10}^{23}}\,{\rm{mo}}{{\rm{l}}^{ - 1}} \times 0.693 \times 1.69 \times {{10}^{ - 13}}}}\)

Therefore, we get the result of:\(x = 0.95218 = 95\% \).

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Most popular questions from this chapter

Energy input is required to fuse medium-mass nuclei, such as iron or cobalt, into more massive nuclei. Explain why.

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.

What is the dose in mSv for: (a) a 0.1 Gy x-ray?

(b) 2.5 mGy of neutron exposure to the eye?

(c) 1.5 mGy of \(\alpha \) exposure?

(a) Calculate the energy released in the neutron-induced fission reaction\(n{ + ^{235}}U{ \to ^{92}}Kr{ + ^{142}}Ba + 2n\),

Given \(m{(^{92}}Kr) = 91.926269{\rm{ }}u\) and

\(m{(^{142}}Ba) = 141.916361{\rm{ }}u\).

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

The laser system tested for inertial confinement can produce a \(100 - kJ\) pulse only \(1.00{\rm{ }}ns\) in duration.

(a) What is the power output of the laser system during the brief pulse?

(b) How many photons are in the pulse, given their wavelength is \(1.06{\rm{ }}\mu m\)?

(c) What is the total momentum of all these photons?

(d) How does the total photon momentum compare with that of a single \(1.00{\rm{ }}MeV\) deuterium nucleus?

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