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Following process is known as, \(h \nu \rightarrow e^{+}+e^{-}\)
(a) When an energetic \(\gamma\)-ray photon falls on a heavy substance, it is absorbed by some nucleus of the substance and an electron and positron are emitted. This phenomenon is called pair production.
The operation of a nuclear reactor is said to be critical, if the multiplication factor ( \(k\) ) has a value
(a) A nuclear reactor is in a critical state when the neutron population remains constant over time.
This means the rate of neutron production equals the rate of neutron loss.
The operation of a nuclear reactor is said to be critical if the multiplication factor \((k)\) has a value of 1.
Which of the following isotopes is used for the treatment of cancer?
(b) \(\mathbf{C o}^{\mathbf{6 0}}\). Cobalt-60 is a radioactive isotope used in radiation therapy for cancer treatment. It emits gamma rays that are directed at tumors to damage the DNA of cancer cells and prevent their growth and division. This technique is also known as cobalt therapy.
When the number of nucleons in nuclei increase, then the binding energy per nucleon
(d) first increases and then decreases with increase of mass number.
Explanation:
Initial Increase:
As the number of nucleons (protons and neutrons) increases in a nucleus, the binding energy per nucleon generally increases initially. This is because the strong nuclear force, which holds the nucleus together, is more effective in smaller nuclei. The strong force is short-range, meaning each nucleon primarily interacts with its immediate neighbors.
Reaching a Maximum:
As the nucleus grows larger, the attractive forces from neighboring nucleons become less effective, and the repulsive forces between protons start to play a more significant role. The binding energy per nucleon reaches a maximum around iron56.
Decreasing for Larger Nuclei:
For even larger nuclei (mass number significantly higher than iron), the binding energy per nucleon starts to decrease. This is because the long-range repulsive forces between protons start to dominate, and the nucleus becomes less stable.
The binding energy per nucleon is maximum in the case of
(b) Binding energy per nucleon increases with atomic number and is maximum for iron. After that it decrease. \({ }_{26}^{56} \mathrm{Fe}\) (Iron-56) has a BE/A of approximately 8.79 MeV. It is known to have the highest binding energy per nucleon among all nuclides.
Which of the following process will result into fission reaction?
(b) Understanding Fission: Fission is a nuclear reaction in which the nucleus of an atom splits into two or more smaller nuclei, along with the release of energy and neutrons. For fission to occur, the nucleus must absorb a neutron and become unstable.
Uranium Isotopes:
U-235 is a fissile isotope, meaning it can sustain a fission chain reaction when it absorbs a neutron.
U-238 is not fissile but can undergo fission under certain conditions, typically when bombarded with fast neutrons.
Neutron Bombardment:
When U-235 is bombarded with fast-moving neutrons, it can absorb the neutron and form U-236, which is unstable and can undergo fission. However, fast neutrons are less likely to cause fission in U-235 compared to thermal neutrons.
When U-235 is bombarded with thermal (slow-moving) neutrons, it is more likely to absorb the neutron and become U236, leading to fission. This is because thermal neutrons have a higher probability of being captured by the nucleus.
U-238 Interaction:
U-238 can also undergo fission when bombarded with fast neutrons, but it is not as efficient as U-235 with thermal neutrons. \(\mathrm{U}-238\) can capture a thermal neutron to become \(\mathrm{U}-239\), which is not a fission reaction but can lead to the production of plutonium-239, which is fissile.
Conclusion: The process that results in a fission reaction is when U-235 is bombarded with thermal neutrons. This leads to the formation of U-236, which is unstable and undergoes fission.
Final Answer: The process that will result in a fission reaction is when U-235 is bombarded with thermal neutrons.
Suppose we consider a large number of containers each containing initially 10000 atoms of a radioactive material with a half-life of 1 year. After 1 yr, [NCERT Exemplar]
(c) The initial number of atoms is \(N_0=10000\).
After one half-life, the average number of atoms remaining is \(\frac{N_0}{2}\).
\(
N_{a v g}=\frac{10000}{2}=5000
\)
Radioactive decay is a statistical process.
While the average number of atoms after one half-life is 5000 , individual containers will show variations.
The actual number of atoms in each container will fluctuate around this average.
Option (a) is incorrect because not all containers will have exactly 5000 atoms due to randomness.
Option (b) is incorrect because the number of atoms will not be the same in all containers.
Option (d) is incorrect as some containers might statistically have slightly more than 5000 atoms.
Option (c) correctly states that containers will have different numbers of atoms, but their average will be close to 5000.
The principle of controlled chain reaction is used in
(a) The principle of controlled chain reaction is used in atomic energy reactor.
Explanation: A controlled chain reaction means that the rate of fission reactions is carefully managed to produce a steady amount of energy, which is the key function of a nuclear reactor.
Key points about the options:
(b) Atom bomb:Â An atom bomb uses an uncontrolled chain reaction, where the fission process rapidly escalates, causing a large explosion.
(c) The core of the sun:Â The energy production in the sun is primarily through nuclear fusion, not fission, and the process is not considered a controlled chain reaction.
(d) Artificial radioactivity:Â Artificial radioactivity involves creating unstable isotopes by bombarding stable nuclei with particles, not a chain reaction.
In an atomic bomb, the energy is released due to
(a) To sustain a chain reaction in atom bomb one of the neutrons emitted in the fission of \({ }^{235} \mathrm{U}\) must be captured by another \({ }^{235} \mathrm{U}\) nucleus and causes its fission.
Expplanation: When uranium -235 is bombarded by neutrons, each uranium nucleus is broken into two nearly equal fragments and along with it huge energy and two ot three fresh neutron are liberated. Under favourable conditions. These neutrons fission other uranium nuclei in the same way. Thus, a chain of nuclear fissions is established which continues until the whole of the uranium is consumed.
Boron rods are used in nuclear reactors because
(a) Boron rods are used in nuclear reactors because boron can absorb neutrons.
Explanation: Boron rods are designed to control the nuclear chain reaction by absorbing excess neutrons, preventing them from causing further fission.
Why other options are incorrect:
(b) strength is given to the plant: Boron rods do not provide structural strength to the reactor.
(c) boron speeds up neutrons: Boron actually slows down the chain reaction by absorbing neutrons, not speeding them up.
(d) the reactors look good: Boron rods have no aesthetic function; their sole purpose is to control the nuclear reaction.
The decay constant of radioactive element is \(1.5 \times 10^{-9} \mathrm{~s}^{-1}\). Its mean life (in s) will be
\(
\text { (c) Mean life, } \tau=\frac{1}{\lambda}=\frac{1}{15 \times 10^{-9}}=6.67 \times 10^8 \mathrm{~s}
\)
A nuclear reaction along with the masses of the particle taking part in it is as follows
\(
\underset{\substack{1.002 \\ \text { amu }}}{A}+\underset{\substack{1.004 \\ \text { amu }}}{B} \rightarrow \underset{\substack{1.001 \\ \text { amu }}}{C}+\underset{\substack{1.003 \\ \text { amu }}}{D}+Q \mathrm{MeV}
\)
The energy \(Q\) liberated in the reaction is
\(
\begin{aligned}
(d) Q & =(1.002+1.004-1.001-1.003)(931.5) \mathrm{MeV} \\
& =1.863 \mathrm{MeV}
\end{aligned}
\)
The curve of binding energy per nucleon as a function of atomic mass number has a sharp peak for helium nucleus. This implies that helium
(b) Helium is very stable. A sharp peak in the curve of binding energy per nucleon indicates high stability for that nucleus. The elements high on the BE versus mass number plot are very tightly bound and hence are stable. And the elements those are lower on this plot, are less tightly bound and hence are unstable.
Since, helium nucleus shown a peak on this plot, so it is very stable.
Explanation:
Binding Energy per Nucleon: This value represents the average energy needed to remove a nucleon (proton or neutron) from the nucleus. A higher binding energy per nucleon implies a more stable nucleus.Â
Peak for Helium: The curve of binding energy per nucleon has a prominent peak at helium (specifically, helium -4 , which has 2 protons and 2 neutrons). This peak signifies that helium nuclei are exceptionally stable.
Stability: Since the peak indicates high binding energy, it means a significant amount of energy is required to break apart a helium nucleus. This makes it very difficult to break apart and, therefore, very stable.
In the given nuclear reaction \(A, B, C, D\) and \(E\) represents
\(
{ }_{92} \mathrm{U}^{238} \xrightarrow{\alpha}{ }_B \mathrm{Th}^A \xrightarrow{\beta}{ }_D \mathrm{~Pa}^C \xrightarrow{E}{ }_{92} \mathrm{U}^{234}
\)
(a) \({ }_{92} \mathrm{U}^{238} \xrightarrow{\alpha}{ }_{90} \mathrm{Th}^{234} \xrightarrow{\beta}{ }_{91} \mathrm{~Pa}^{234} \xrightarrow{\beta}{ }_{92} \mathrm{U}^{234}\)
So, \(\quad A=234, B=90, C=234, D=91\) and \(E=\beta\)
Explanation: The initial reaction is:
\(
{ }_{92} \mathrm{U}^{238} \rightarrow \text { (alpha particle) }+{ }_B \mathrm{Th}^A
\)
Here, Uranium-238 (U-238) undergoes alpha decay.
An alpha particle consists of 2 protons and 2 neutrons, which means it has a mass number of 4 and an atomic number of 2. When U-238 emits an alpha particle, the new element formed will have:
Mass number: \(238-4=234\)
Atomic number: \(92-2=90\)
Thus, we have:
\(
A=234, \quad B=90
\)
The resulting element is Thorium (Th).
The first decay product is:
\(
{ }_{90} \mathrm{U}^{234}} \rightarrow \text { (beta particle) }+{ }_D \mathrm{~Pa}^C
\)
Here, Thorium-234 undergoes beta decay.
In beta decay, a neutron is converted into a proton, resulting in:
Mass number remains the same: 234
Atomic number increases by 1: \(90+1=91\)
Thus, we have:
\(
C=234, \quad D=91
\)
The resulting element is Protactinium (Pa).
\(
{ }_{91} \mathrm{Pa}^{234}} \rightarrow(\mathrm{E})+{ }_{92} \mathrm{U}^{234}}
\)
Here, Protactinium-234 undergoes decay to form Uranium-234.
In this case, since the atomic number increases from 91 to 92 while the mass number remains the same, this indicates that a beta particle is emitted.
Thus, we have:
\(
E=\text { beta particle }
\)
Final Values
Now, we can summarize the values:
\(A=234\)
\(B=90\)
\(C=234\)
\(D=91\)
\(E=\) beta particle
An atom of mass number 15 and atomic number 7, captures an \(\alpha\)-particle and then emits a proton. The mass number and atomic number of the resulting product will respectively be
\(
(d){ }_7 X^{15}+\alpha \text {-particle } \longrightarrow{ }_9 Y^{19} \xrightarrow{{ }_1 \mathrm{H}^1}{ }_8 \mathrm{Z}^{18}
\)
Explanation: Initial mass number: 15
Mass number of \(\alpha\)-particle: 4
Mass number after capture: \(15+4=19\)
Calculate the atomic number after capturing an \(\alpha\)-particle.
Initial atomic number: 7
Atomic number of \(\alpha\)-particle: 2
Atomic number after capture: \(7+2=9\)
Calculate the final mass number after emitting a proton.
Mass number after capture: 19
Mass number of proton: 1
Final mass number: \(19-1=18\)
Calculate the final atomic number after emitting a proton.
Atomic number after capture: 9
Atomic number of proton: 1
Final atomic number: \(9-1=8\)
The mass number and atomic number of the resulting product are 18 and 8 respectively.
The binding energies of the nuclei \(A\) and \(B\) are \(E_a\) and \(E_b\), respectively. Three atoms of the element \(B\) fuse to give one atom of element \(A\) and an energy \(Q\) is released. Then, \(E_a, E_b\) and \(Q\) are related as
\(
\begin{aligned}
&\text { (a) Three atoms of } B \longrightarrow \text { one atom of } A\\
&\therefore \quad Q=E_a-3 E_b
\end{aligned}
\)
The total number of \(\alpha\) and \(\beta\) particles emitted in the nuclear reaction
\({ }_{92}^{238} \mathrm{U} \longrightarrow{ }_{82}^{214} \mathrm{~Pb}\) is
(c) \({ }_{92}^{238} \mathrm{U} \longrightarrow{ }_{82}^{214} \mathrm{~Pb}+6{ }_2^4 \mathrm{He}+2{ }_{-1}^0 e\)
The total number of \(\alpha\) and \(\beta\)-particles emitted in the nuclear reaction is 8.
Explanation: Let \(x\) be the number of alpha particles and \(y\) be the number of beta particles.
\(
{ }_{92}^{238} \mathrm{U} \rightarrow{ }_{82}^{214} \mathrm{~Pb}+x \cdot{ }_2^4 \mathrm{He}+y \cdot{ }_{-1}^0 \mathrm{e}
\)
The sum of mass numbers on both sides must be equal.
\(
\begin{aligned}
& 238=214+4 x+0 y \\
& 238=214+4 x \\
& 4 x=238-214 \\
& 4 x=24 \\
& x=\frac{24}{4}=6
\end{aligned}
\)
The sum of atomic numbers on both sides must be equal.
\(
\begin{aligned}
& 92=82+2 x+(-1) y \\
& 92=82+2 x-y
\end{aligned}
\)
Substitute the value of \(x=6\) :
\(
\begin{aligned}
& 92=82+2(6)-y \\
& 92=82+12-y \\
& 92=94-y \\
& y=94-92 \\
& y=2
\end{aligned}
\)
\(
\begin{aligned}
& \text { Total particles }=\text { number of alpha particles }+ \text { number of beta particles. } \\
& \text { Total particles }=x+y=6+2=8 \text {. }
\end{aligned}
\)
\(90 \%\) of a radioactive sample is left undecayed after time \(t\) has elapsed. What percentage of the initial sample will decay in a total time \(2 t\)?
(b) Let \(N(t)\) be the amount of radioactive material remaining after time \(t\). The radioactive decay law states that \(N(t)=N_0 e^{-\lambda t}\), where \(N_0\) is the initial amount and \(\lambda\) is the decay constant.
Given that \(90 \%\) of the sample is left undecayed after time \(t\), we have:
\(
\begin{aligned}
& 0.9 N_0=N_0 e^{-\lambda t} \\
& 0.9=e^{-\lambda t}
\end{aligned}
\)
We want to find the percentage of the initial sample that decays in time \(2 t\). Let \(N(2 t)\) be the amount remaining after time \(2 t\).
\(
\begin{aligned}
& N(2 t)=N_0 e^{-2 \lambda t} \\
& N(2 t)=N_0\left(e^{-\lambda t}\right)^2 \\
& N(2 t)=N_0(0.9)^2 \\
& N(2 t)=N_0(0.81)
\end{aligned}
\)
So, \(81 \%\) of the initial amount remains undecayed after time \(2 t\). The percentage of the initial sample that decayed is:
\(
100 \%-81 \%=19 \%
\)
Therefore, \(19 \%\) of the initial sample will decay in a total time \(2 t\).
Half-life of a radioactive substance is 20 min. The time between \(20 \%\) and \(80 \%\) decay will be
(b) Here, half-life of radioactive substance, \(T_{1 / 2}=20 \mathrm{~min}\) We have, \(N=N_0\left(\frac{1}{2}\right)^{t / T_{1 / 2}}\)
So, for \(20 \%\) decay, \(\frac{N}{N_0}=\frac{80}{100}=\left(\frac{1}{2}\right)^{t_1 / 20} \dots(i)\)
For \(80 \%\) decay, \(\frac{N}{N_0}=\frac{20}{100}=\left(\frac{1}{2}\right)^{t_2 / 20} \dots(ii)\)
On dividing Eq. (ii) by Eq. (i), we get
\(
\left(\frac{1}{2}\right)^{\left(\frac{t_2-t_1}{20}\right)}=\frac{1}{4} \quad \text { or } \quad\left(\frac{1}{2}\right)^{\left(\frac{t_2-t_1}{20}\right)}=\left(\frac{1}{2}\right)^2
\)
On comparing the exponents,
\(
\frac{t_2-t_1}{20}=2 \Rightarrow t_2-t_1=40 \mathrm{~min}
\)
\(\therefore\) The time between \(20 \%\) and \(80 \%\) decay \(t_2-t_1=40 \mathrm{~min}\)
A freshly prepared radioactive source of half-life 2 h emits radiation of intensity which is 64 times the permissible safe level. The minimum time after which it would be possible to work safely with this source is
(d) After \(n\) number of half-life, \(N=N_0\left(\frac{1}{2}\right)^n\)
\(
1=64\left(\frac{1}{2}\right)^n \Rightarrow\left(\frac{1}{2}\right)^6=\left(\frac{1}{2}\right)^n
\)
\(n=6\), i.e. 6 half-lives
\(\therefore\) Minimum time, \(t=6 \times 2=12 \mathrm{~h}\)
A radioactive substance disintegrates \(1 / 64\) of initial value in 60 s. The half-life of this substance is
(b) We have, \(\frac{1}{64}=\left(\frac{1}{2}\right)^n\)
\(
n=6
\)
6 half-lives are equal to 60 s.
\(
\therefore 1 \text { half-life }=10 \mathrm{~s}
\)
In the reaction \({ }_1^2 \mathrm{H}+{ }_1^3 \mathrm{H} \rightarrow{ }_2^4 \mathrm{He}+{ }_0 n^1\), if the binding energies of \({ }_1^2 \mathrm{H},{ }_1^3 \mathrm{H}\) and \({ }_2^4 \mathrm{He}\) are respectively, \(a, b\) and \(c\) (in MeV ), then the energy (in MeV ) released in this reaction is
(b) The nuclear reaction is \({ }_1^2 \mathrm{H}+{ }_1^3 \mathrm{H} \rightarrow{ }_2^4 \mathrm{He}+{ }_0 n^1\).
The binding energy of \({ }_1^2 \mathrm{H}\) is \(a \mathrm{MeV}\).
The binding energy of \({ }_1^3 \mathrm{H}\) is \(b \mathrm{MeV}\).
The binding energy of \({ }_2^4 \mathrm{He}\) is \(c \mathrm{MeV}\).
Energy released in a nuclear reaction is the difference between the total binding energy of products and reactants.
A free neutron has no binding energy.
Calculate the total binding energy of the reactants:
The reactants are \({ }_1^2 \mathrm{H}\) and \({ }_1^3 \mathrm{H}\).
Total binding energy of reactants: \(B E_{\text {reactants }}=a+b\).
Calculate the total binding energy of the products:
The products are \({ }_2^4 \mathrm{He}\) and \({ }_0 n^1\).
The binding energy of \({ }_2^4 \mathrm{He}\) is \(c\).
The binding energy of a free neutron \(0^n\) is 0.
Total binding energy of products: \(B E_{\text {products }}=c+0=c\).
Energy released is the difference between the total binding energy of products and reactants.
Energy released \(=\boldsymbol{B} E_{\text {products }}-\boldsymbol{B} E_{\text {reactants }}\).
Energy released \(=c-(a+b)\).
Energy released \(=c-a-b\).
A radioactive sample has \(N_0\) active atoms at \(t=0\). If the rate of disintegration at any time is \(R\) and the number of atoms is \(N\), then the ratio \(R / N\) varies with time as
(d) Rate, \(R=\lambda N\)
\(
\therefore \quad \frac{R}{N}=\lambda \text { (constant) }
\)
So, graph between \(R / N\) and \(t\) be a straight line parallel to the time axis.
The plot of the number \((N)\) of decayed atoms versus activity \((R)\) of a radioactive substance is
(d) We have, \(N=N_0 e^{-\lambda t}\) and \(R=R_0 e^{-\lambda t}=\lambda N_0 e^{-\lambda t}\)
\(
\left(\because R_0=\lambda N_0\right)
\)
\(
\therefore \quad N_{\text {decayed }}=N_0-N=N_0-N_0 e^{-\lambda t}=N_0-\frac{R}{\lambda}
\)
This is the equation of straight line with negative slope.
The graph between the instantaneous concentration \((N)\) of a radioactive element and time \((t)\) is
(d) By using, \(N=N_0 e^{-\lambda t}\)
It shows that \(N\) decreases exponentially with time.
Two radioactive materials \(X_1\) and \(X_2\) have decay constants \(10 \lambda\) and \(\lambda\), respectively. If initially they have the same number of nuclei, then the ratio of the number of nuclei of \(X_1\) to that of \(X_2\) will be \(1 / e\) after a time
\(
\text { (d) We have, } \frac{1}{e}=\frac{N_0 e^{-10 \lambda t}}{N_0 e^{-\lambda t}}=e^{-9 \lambda t} \text { or } t=\frac{1}{9 \lambda}\left(\because \text { given, } \frac{N_1}{N_2}=\frac{1}{e}\right)
\)
Two radioactive nuclei \(A\) and \(B\) have disintegration constants \(\lambda_A\) and \(\lambda_B\) and initially \(N_A\) and \(N_B\) number of nuclei of them are taken, then the time after which their undisintegrated nuclei are same, is
\(
\begin{aligned}
& (c) \text { We have, } N_A e^{-\lambda_A t}=N_B e^{-\lambda_B t} \\
& \therefore \quad e^{\left(\lambda_B-\lambda_A\right) t}=\frac{N_B}{N_A} \\
& \therefore \text { Time, } t=\frac{1}{\lambda_B-\lambda_A} \ln \left(\frac{N_B}{N_A}\right)
\end{aligned}
\)
What is the binding energy per nucleon of \({ }_6 \mathrm{C}^{12}\) nucleus?
Given, mass of \(\mathrm{C}^{12}\left(m_C\right)=12.000 \mathrm{u}\),
Mass of proton \(\left(m_p\right)=1.0078 \mathrm{u}\),
Mass of neutron \(\left(m_n\right)=1.0087 \mathrm{u}\) and \(1 \mathrm{amu}=931.4 \frac{\mathrm{MeV}}{c^2}\).
\(
\begin{aligned}
&\text { (d) Binding energy per nucleon }\\
&\begin{aligned}
& =\frac{\left[\left\{m_p Z+m_n(A-Z)\right\}-M\right] \times 9314}{\text { Mass number }(A)} \\
& =\left(\frac{6 \times 1.0078+6 \times 1.0087-12}{12}\right) \times 931.4 \\
& =7.68 \mathrm{MeV}
\end{aligned}
\end{aligned}
\)
A radioactive isotope \(X\) with a half-life of \(1.37 \times 10^9 \mathrm{yr}\) decays to \(Y\) which is stable. A sample of rock from the moon was found to contain both the elements \(X\) and \(Y\) which were in the ratio of \(1: 7\). The age of the rock is
(c) If in the rock there is no \(Y\) element, then the time taken by element \(X\) to reduce to \(\left(\frac{1}{8}\right)\) th the initial value will be equal to
\(
\frac{1}{8}=\left(\frac{1}{2}\right)^n \text { or } n=3
\)
Therefore, from the beginning three half-life time is spent. Hence, the age of the rock is
\(
=3 \times 1.37 \times 10^9=4.11 \times 10^9 \mathrm{yr}
\)
If the energy released in the fission of one nucleus is 200 MeV , then the number of nuclei required per second in a power plant of 16 kW will be
(d) Energy released in the fission of one nucleus \(=200 \mathrm{MeV}\)
\(
\begin{aligned}
& =200 \times 10^6 \times 1.6 \times 10^{-19}=3.2 \times 10^{-11} \mathrm{~J} \\
P & =16 \mathrm{~kW}=16 \times 10^3 \mathrm{~W}
\end{aligned}
\)
Now, number of nuclei required per second
\(
n=\frac{P}{E}=\frac{16 \times 10^3}{3.2 \times 10^{-11}}=5 \times 10^{14}
\)
A common example of \(\beta\)-decay is
\(
{ }_{15} \mathrm{P}^{32} \rightarrow{ }_{16} \mathrm{P}^{32}+x+y
\)
Then, \(x\) and \(y\) stand for
(c) In \(\beta^{-}\)decay, a neutron in the nucleus is transformed into a proton, an electron and an anti-neutrino.
\(
n \rightarrow P+\bar{e}+\bar{\nu}
\)
So, \(x\) and \(y\) stand for electron and anti-neutrino.
Explanation:
The atomic number (subscript) increases from 15 to 16.
This indicates a \(\beta^{-}\)-decay, where a neutron converts to a proton.
In \(\beta^{-}\)-decay, an electron ( \(\mathrm{e}^{-}\) or \(\beta^{-}\)) and an electron antineutrino ( \(\bar{\nu}}\) ) are emitted.
Therefore, \(x\) and \(y\) represent an electron and an antineutrino.
A nucleus with \(Z=92\) emits the following in a sequence \(\alpha, \beta^{-}, \beta^{-}, \alpha, \alpha, \alpha, \alpha, \alpha, \beta^{-}, \beta^{-}, \alpha, \beta^{+}, \beta^{+}, \alpha\). The \(Z\) of the resulting nucleus is
(c) Alpha ( \(\alpha\) ) emission decreases \(Z\) by 2 .
Beta-minus ( \(\beta^{-}\)) emission increases \(Z\) by 1 .
Beta-plus \(\left(\beta^{+}\right)\) emission decreases \(Z\) by 1 .
Number of \(\alpha\) emissions: 8
Number of \(\beta^{-}\)emissions: 4
Number of \(\beta^{+}\)emissions: 2
Change due to \(\alpha\) emissions: \(\Delta Z_\alpha=8 \times(-2)=-16\)
Change due to \(\beta^{-}\)emissions: \(\Delta \boldsymbol{Z}_{\beta^{-}}=4 \times(1)=4\)
Change due to \(\beta^{+}\)emissions: \(\Delta Z_{\beta^{+}}=2 \times(-1)=-2\)
Total change: \(\Delta Z_{\text {total }}=\Delta Z_\alpha+\Delta Z_{\beta^{-}}+\Delta Z_{\beta^{+}}\) \(\Delta Z_{\text {total }}=-16+4-2=-14\)
Final \(Z=\) Initial \(Z+\Delta Z_{\text {total }}\)
Final \(Z=92+(-14)=78\)
Binding energy per nucleon versus mass number curve for nuclei is shown in the figure. \(W, X, Y\) and \(Z\) are four nuclei indicated on the curve. The process that would release energy is
(c) Energy is released in a process when total binding energy (BE) of the nucleus is increased or we can say when total BE of products is more than the reactants. By calculation, we can see that only in case of option (c), this happens.
Given, \(W \rightarrow 2 Y\)
BE of reactants \(=120 \times 7.5=900 \mathrm{MeV}\) and BE of products \(=2 \times 60 \times 8.5=1020 \mathrm{MeV}\)
i.e. \mathrm{BE}[/latex] of products \(>\mathrm{BE}\) of reactants.
Hence, energy is released in the process of option (c).
A stationary radioactive nucleus of mass 210 units disintegrates into an alpha particle of mass 4 units and residual nucleus of mass 206 units. If the kinetic energy of the alpha particle is \(E\), then the kinetic energy of the residual nucleus is
(b) Momentum remains constant.
\(
\begin{array}{ll}
\therefore & K=\frac{p^2}{2 m} \text { or } K \propto \frac{1}{m} \\
\Rightarrow & \frac{K_n}{K_\alpha}=\frac{m_\alpha}{m_n}=\frac{4}{206}=\frac{2}{103}
\end{array}
\)
\(\therefore\) Kinetic energy of the residual nucleus
\(
K_n=\left(\frac{2}{103}\right) K_\alpha=\left(\frac{2}{103}\right) E
\)
Assuming that about 200 MeV energy is released per fission of \({ }_{92} \mathrm{U}^{235}\) nuclei. What would be the mass of \(\mathrm{U}^{235}\) consumed per day in the fission of reactor of power 1 MW approximately?
(c) As, \(n=\frac{m}{A} N_A \Rightarrow E=\left(\frac{m}{A} N_A \times 200 \times 1.6 \times 10^{-13}\right) \mathrm{J}\)
For 1 day \(=24 \times 3600\)
Power \(=\frac{E}{t}=\frac{m N_A \times 3.2 \times 10^{-11}}{235 \times 24 \times 3600}=10^6 \quad\left(\because\right.\) given, \(\left.P=10^6 \mathrm{~W}\right)\)
\(\therefore\) Mass, \(m=\frac{1 \times 10^6 \times 24 \times 3600 \times 235}{3.2 \times 10^{-11} \times 6.02 \times 10^{23}} \approx 1 \mathrm{~g}\)
In the nuclear fusion reaction \({ }_1^2 \mathrm{H}+{ }_1^3 \mathrm{H} \rightarrow{ }_2^4 \mathrm{He}+{ }_0^1 n\), given that the repulsive potential energy between the two nuclei is \(-7.7 \times 10^{-14} \mathrm{~J}\). The temperature at which the gases must be heated to initiate the reaction is of the order of [Boltzmann’s constant, \(k=1.38 \times 10^{-23} \mathrm{~J} / \mathrm{K}\) ]
(a) Kinetic energy of the molecules of a gas at a temperature \(T\) is \(\frac{3}{2} k T\).
\(\therefore\) To initiate the reaction \(\frac{3}{2} k T=7.7 \times 10^{-14} \mathrm{~J}\)
\(
\begin{array}{rlr}
\Rightarrow & \frac{3}{2} \times 1.38 \times 10^{-23} \mathrm{~T} & =7.7 \times 10^{-14} \\
\Rightarrow & T =3.7 \times 10^9 \mathrm{~K}
\end{array}
\)
Thus, the order of temperature is \(10^9 \mathrm{~K}\).
A star initially has \(10^{40}\) deuterons. It produces energy via the processes \({ }_1^2 \mathrm{H}+{ }_1^2 \mathrm{H} \rightarrow{ }_1^3 \mathrm{H}+p\) and \({ }_1^2 \mathrm{H}+{ }_1^3 \mathrm{H} \rightarrow{ }_2^4 \mathrm{He}+n\), where the masses of the nuclei are \(m\left({ }^2 \mathrm{H}\right)=2.014 \mathrm{amu}, m(p)=1.007 \mathrm{amu}\), \(m(n)=1.008 \mathrm{amu}\) and \(m\left({ }^4 \mathrm{He}\right)=4.001 \mathrm{amu}\). If the average power radiated by the star is \(10^{16} \mathrm{~W}\), then the deuteron supply of the star is exhausted in a time of the order of
(c) Net process is, \(3{ }_1 \mathrm{H}^2 \rightarrow{ }_2 \mathrm{He}^4+p+n\)
Mass defect, \(\Delta m=(3 \times 2.014)-4.001-1.007-1.008\)
\(
=0.026 \mathrm{amu}
\)
Energy released by the fusion of three deuterons
\(
\begin{aligned}
& =\Delta m \times 931.48=0.026 \times 931.48 \mathrm{MeV} \\
& =0.026 \times 931.48 \times 1.6 \times 10^{-13} \mathrm{~J} \\
& =3.87 \times 10^{-12} \mathrm{~J}
\end{aligned}
\)
\(
\begin{aligned}
&\begin{aligned}
& \begin{aligned}
\therefore \text { Total energy released } & =\frac{10^{40}}{3} \times 3.87 \times 10^{-12} \mathrm{~J} \\
& =1.29 \times 10^{28} \mathrm{~J}
\end{aligned} \\
& \text { Total time }=\frac{1.29 \times 10^{28}}{10^{16}}=1.29 \times 10^{12} \mathrm{~s}\left(\because \text { power }=\frac{\text { energy }}{\text { time }}\right)
\end{aligned}\\
&\therefore \text { The order of time is } 10^{12} \mathrm{~s}
\end{aligned}
\)
Assertion: Radioactive nuclei emits \(\beta\)-particles.
Reason: Electron exist inside the nucleus. [AIIMS 2018]
(c) For a \(\beta\)-decay, \({ }_0^1 n \longrightarrow{ }_1^1 p+{ }_{-1} e^0\) where, \({ }_{-1} e^0\) is an electron emitted in the transformation of a neutron into proton in the radioactive nucleus. But electron does not exist inside the nucleus.
In the fusion reaction, the masses of deuteron, helium and neutron expressed in amu are 2.015, 3.017 and 1.009, respectively. If 1 kg of deuterium undergoes complete fusion, then find the amount of total energy released. ( \(1 \mathrm{amu}=931.5 \mathrm{MeV}\) ) [JIPMER 2018]
\(
\begin{aligned}
& \text { (a) } \begin{aligned}
\Delta m & =2(2015)-(3.017+1.009) \\
& =0.004 \mathrm{amu}
\end{aligned} \\
& \begin{aligned}
\because \text { Energy released } & =(0.004 \times 931.5) \mathrm{MeV} \\
& =3.726 \mathrm{MeV}
\end{aligned}
\end{aligned}
\)
Energy released per deuterium
\(
=\frac{3.726}{2}=1.863 \mathrm{MeV}
\)
Number of deuterons in 1 kg
\(
=\frac{6.02 \times 10^{26}}{2}=3.01 \times 10^{26}
\)
\(\because\) Energy released per kg of deuterium fusion
\(
\begin{aligned}
& =\left(3.01 \times 10^{26} \times 1.863\right) \\
& =5.6 \times 10^{26} \mathrm{MeV} \\
& =9 \times 10^{13} \mathrm{~J}
\end{aligned}
\)
Assertion: In \(\alpha\)-decay, atomic number of daughter nucleus reduces by a unit from the parents nucleus.
Reason: An \(\alpha\)-particle carriers four units of mass. [AIIMS 2017]
(d) We know that, \(\boldsymbol{\alpha}\)-particle carries two units of positive charge and four units of mass. In \(\alpha\)-decays, charge or atomic number of daughter nucleus decreased by two units. Also, mass number reduces by four units.
A nuclear explosive is designed to deliver 1MW power in the form of heat energy. If the explosion is designed with nuclear fuel consisting of \(\mathrm{U}^{235}\) to run a reactor at this power level for one year, then the amount of fuel needed is (Take, energy per fission \(=200 \mathrm{MeV}\) ) [AIIMS 2017]
(d) Energy released per fission,
\(
\begin{aligned}
E & =200 \mathrm{MeV}=200 \times 1.6 \times 10^{-13} \\
& =3.2 \times 10^{-11} \mathrm{~J}
\end{aligned}
\)
Total energy required to run a 1 MW reaction for one year
\(
\begin{aligned}
& =10^6 \mathrm{~J} \mathrm{~s}^{-1} \times(365 \times 24 \times 60 \times 60) \\
& =3.15 \times 10^{13} \mathrm{~J}
\end{aligned}
\)
Since, 1 fission (atom of \(\mathrm{U}^{235}\) ) produces \(3.2 \times 10^{-11} \mathrm{~J}\) of energy.
So, total number of \(\mathrm{U}^{235}\) atoms required is
\(
\frac{3.15 \times 10^{13}}{3.2 \times 10^{-11}}=9.84 \times 10^{23}
\)
\(\because\) Mass of \(\mathrm{U}^{235}\) containing \(9.84 \times 10^{23}\) atom,
\(
\begin{aligned}
M & =\frac{235}{6.02 \times 10^{23}} \times 9.84 \times 10^{23} \\
& =384 \mathrm{~g}=0.384 \mathrm{~kg}
\end{aligned}
\)
Two spherical nuclei have mass numbers 216 and 64 with their radii \(R_1\) and \(R_2\), respectively. The ratio, \(\frac{R_1}{R_2}\) is equal to [AIIMS 2015]
(a) Radius of nuclei having mass number \(A\) is determined as where,
\(
\begin{aligned}
R & =R_0 A^{1 / 3} \\
R_0 & =1.2 \times 10^{-15} \mathrm{~m} \text { (where, } R_0=\text { constant) }
\end{aligned}
\)
This implies, \(\frac{R_1}{R_2}=\left(\frac{A_1}{A_2}\right)^{1 / 3}=\left(\frac{216}{64}\right)^{1 / 3}=\frac{6}{4} \Rightarrow R_1: R_2=3: 2\)
The kinetic energy of \(\alpha\)-particle emitted in the \(\alpha\)-decay of \({ }_{88} \mathrm{Ra}^{226}\) is
[Take, \(m(\mathrm{Ra})=226.02540 \mathrm{u}\),\(m(\mathrm{Rn})=222.01750 \mathrm{u}\) and \(m(\mathrm{He})=4.002603 \mathrm{u}\) ] [UP CPMT 2015]
\(
\text { (d) The reaction should be }{ }_{88} \mathrm{Ra}^{226} \longrightarrow{ }_{86} \mathrm{Rn}^{222}+{ }_2 \mathrm{He}^4
\)
\(
Q \text {-value }=\left[\begin{array}{c}
\text { (mass number of Ra) } \\
-(\text { mass number of Rn }) \\
-m\left(\mathrm{He}^4\right)
\end{array}\right] \mathrm{u} \times 931.5 \mathrm{MeV}
\)
\(
\begin{aligned}
=0.005297 \times 9315 & =4.934 \mathrm{MeV} \\
\text { Energy corresponding mass defect } & =\frac{m(\mathrm{Rn})}{m(\mathrm{Ra})} \times Q \text {-value } \\
& \simeq 4.871 \mathrm{MeV}
\end{aligned}
\)
In a nuclear reactor, the number of \(\mathrm{U}^{235}\) nuclei undergoing fissions per second is \(4 \times 10^{20}\). If the energy released per fission is 250 MeV, then the total energy released in 10 h is \(\left(1 \mathrm{eV}=16 \times 10^{-19} \mathrm{~J}\right)\) [EAMCET 2015]
(b) The fission per second \(=4 \times 10^{20}\)
So, the energy released per second
\(
\begin{aligned}
& =\left(4 \times 10^{20} \times 250\right) \mathrm{MeV} \\
& =\left(4 \times 10^{20} \times 250 \times 10^6 \times 1.6 \times 10^{-19}\right) \mathrm{J}
\end{aligned}
\)
Therefore, energy released in \(10 \mathrm{~h}=36 \times 10^3 \mathrm{~s}\),
\(
\begin{aligned}
E & =\left(36 \times 10^3 \times 4 \times 10^{20} \times 250 \times 10^6 \times 1.6 \times 10^{-19}\right) \mathrm{J} \\
& =\left(36 \times 4 \times 250 \times 1.6 \times 10^{10}\right) \mathrm{J}=\left(57600 \times 10^{10}\right) \mathrm{J} \\
& =576 \times 10^{12} \mathrm{~J}
\end{aligned}
\)
Nuclear fusion is not found in [Kerala CEE 2015]
(d) Nuclear fusion is not found in atom bomb because it works on the phenomenon of nuclear fission.
The approximate ratio of nuclear mass densities of \({ }_{79}^{197} \mathrm{Au}\) and \({ }_{47}^{107} \mathrm{Ag}\) nuclei is [Kerala CEE 2015]
(d) Nuclear mass density is independent of mass number, therefore ratio of nuclear mass densities of \(\mathrm{Au}^{197}\) and \(\mathrm{Ag}^{107}\) is \(1: 1\).
A radioactive element \(X\) disintegrates successively
\(
X \xrightarrow{\beta^{-}} X_1 \xrightarrow{\alpha} X_2 \xrightarrow{\beta^{-}} X_3 \xrightarrow{\alpha} X_4
\)
If atomic number and atomic mass number of \(X\) are respectively, 72 and 180 , then what are the corresponding values for \(X_4\)? [Guj. CET 2015]
(d) In \(\beta^{-}\)decay, the atomic number increases by 1 and the mass number remains unchanged.
In \(\alpha\) decay, the atomic number decreases by 2 and the mass number decreases by 4.
Atomic number of \(X_1: Z_{X_1}=Z_X+1=72+1=73\).
Mass number of \(X_1: A_{X_1}=A_X=180\).
Atomic number of \(X_2: Z_{X_2}=Z_{X_1}-2=73-2=71\).
Mass number of \(X_2: A_{X_2}=A_{X_1}-4=180-4=176\).
Atomic number of \(X_3: Z_{X_3}=Z_{X_2}+1=71+1=72\).
Mass number of \(X_3: A_{X_3}=A_{X_2}=176\).
Atomic number of \(X_4: Z_{X_4}=Z_{X_3}-2=72-2=70\).
Mass number of \(X_4: A_{X_4}=A_{X_3}-4=176-4=172\).
The atomic number and atomic mass number of \(X_4\) are 70 and 172 respectively.
The energy released by the fission of one uranium atom is 200 MeV. The number of fission per second required to produce 6.4 W power is [Guj. CET 2015]
(a) Let there is \(n\) number of fission per second produces a power of 6.4 W , then
\(
\begin{gathered}
n \times 200 \times 10^6 \times 1.6 \times 10^{-19}=6.4 \\
\therefore \quad n=\frac{6.4}{200 \times 10^{-13} \times 1.6}=\frac{4}{2 \times 10^{-11}}=2 \times 10^{11}
\end{gathered}
\)
By the successive disintegration of \({ }_{92} \mathrm{U}^{238}\), the final product obtained is \({ }_{82} \mathrm{~Pb}^{206}\), then how many number of \(\alpha\) and \(\beta\)-particles are emitted? [Guj. CET 2015]
(b) The number of \(\alpha\)-particles, \(n_1\)
\(
=\frac{\text { change in mass number }}{4}=\frac{238-206}{4} \Rightarrow n_1=\frac{32}{4}=8
\)
Now, number of \(\beta\)-particles, \(n_2=82-\left(92-2 n_1\right)\)
\(
=82-(92-2 \times 8)=82-76=6
\)
A nucleus at rest splits into two nuclear parts having radii in the ratio \(1: 2\). Their velocities are in the ratio [KCET 2015]
(b) Given, \(\frac{R_1}{R_2}=\frac{1}{2}\)
According to conservation of linear momentum, we have
\(
m_1 v_1=m_2 v_2
\)
\(
\frac{v_1}{v_2}=\frac{m_2}{m_1}=\left(\frac{R_2}{R_1}\right)^3 \quad\left(\because m \propto v \propto R^3\right)
\)
\(
\frac{v_1}{v_2}=\left(\frac{2}{1}\right)^3=\frac{8}{1}
\)
What is the energy released by fission of 1 g of \(\mathrm{U}^{235}\)? (Assume 200 MeV energy is liberated on fission of 1 nucleus) [CG PMT 2015]
(a) Energy released in one fission of \({ }_{92}^{235} \mathrm{U}\) nucleus \(=200 \mathrm{MeV}\) Mass of uranium \(=1 \mathrm{~g}\)
We know that, 235 g of \({ }^{235} \mathrm{U}\) has \(6.023 \times 10^{23}\) atoms or nuclei.
\(\therefore\) Energy released in fission of 1 g of \(\mathrm{U}^{235}\),
\(
\begin{aligned}
E & =\frac{6.023 \times 10^{23} \times 1 \times 200}{235}=5.1 \times 10^{23} \mathrm{MeV} \\
& =\left(5.1 \times 10^{23} \times 1.6 \times 10^{-13}\right) \mathrm{J} \\
& =\frac{5.1 \times 10^{23} \times 1.6 \times 10^{-13}}{3.6 \times 10^6} \mathrm{kWh}=2.26 \times 10^4 \mathrm{kWh}
\end{aligned}
\)
The half-life of radium is 1620 yr and its atomic weight is 226 kg per kilo mol. The number of atoms that will decay from its 1 g sample per second will be (Take, Avogadro’s number, \(N_A=6.023 \times 10^{23}\) atom \(/ \mathrm{mol}\) ) [Manipal 2015]
(a) We have, \(\frac{d N}{d t}=\lambda N\) and
\(
\lambda=\frac{0.6931}{T_{1 / 2}}=\frac{0.6931}{1620 \times 365 \times 24 \times 60 \times 60}
\)
Total number of atoms, \(N=\frac{6.023 \times 10^{23}}{226}\)
\(
\therefore \frac{d N}{d t}=\frac{0.6931 \times 6.023 \times 10^{23}}{1620 \times 365 \times 24 \times 60 \times 60 \times 226}=3.61 \times 10^{10}
\)
The relationship between decay constant \(\lambda\) and half-life \(T\) of a radioactive substance is [UP PMT 2015]
(b) The relation between decay constant \(\lambda\) and half-life \(T\) can be given as
\(
\begin{array}{rlrl}
& & T & =\frac{0.693}{\lambda} \\
\therefore & \lambda & =\frac{\log _e 2}{T}
\end{array}
\)
For the stability of any nucleus,
(a) The binding energy of a nucleus is the energy required to take its nucleons away from one another. It is generally expressed as binding energy per nucleon. It is a measure of the stability of the nucleus. Higher the binding energy per nucleon, more stable is the nucleus.
A uranium nucleus \({ }_{92} \mathrm{U}^{238}\) emits an \(\alpha\)-particle and a \(\beta\)-particle in succession. The atomic number and mass number of the final nucleus will be [Kerala CEE 2014]
(d) An \(\alpha\)-particle is a helium nucleus, \({ }_2^4 \mathrm{He}\). A \(\beta\)-particle is an electron, \({ }_{-1}^0 \mathrm{e}\).
An \(\alpha\)-particle emission reduces the atomic number by 2.
An \(\alpha\)-particle emission reduces the mass number by 4.
New atomic number: \(Z^{\prime}=92-2=90\).
New mass number: \(A^{\prime}=238-4=234\).
A \(\beta\)-particle emission increases the atomic number by 1.
A \(\beta\)-particle emission does not change the mass number.
Final atomic number: \(Z^{\prime \prime}=90+1=91\).
Final mass number: \(A^{\prime \prime}=234+0=234\).
The atomic number of the final nucleus is 91 and the mass number is 234.
For the radioactive nuclei that undergo either $\alpha$ or $\beta$ decay, which one of the following cannot occur? [WB JEE 2014]
(b) Isotope of the original nucleus is produced: Not possible as atomic number always changes in both \(\alpha\) and \(\beta\) decay.
(a) Isobar of original nucleus is produced: Possible in \(\beta\) decay.
(c) Nuclei with higher atomic number than that of the original nucleus is produced: Possible in \(\beta^{-}\)decay.
(d) Nuclei with lower atomic number than that of the original nucleus is produced: Possible in \(\alpha\) and \(\beta^{+}\)decay.
In a given reaction,
\(
{ }_z X^A \rightarrow{ }_{z+1} Y^A \rightarrow{ }_{z-1} \mathrm{~K}^{A-4} \rightarrow{ }_{z-1} \mathrm{~K}^{A-4}
\)
The radioactive radiations are emitted in the sequence of [UK PMT 2014]
(c) Suppose a given nucleus is \({ }_Z X^A\).
In \(\alpha\)-decay, the mass number of the product nucleus is four less than that of decaying nucleus, while the atomic number decreases by two.
\(
{ }_Z X^A \xrightarrow{\alpha-\text { decay }}{ }_{Z-2} X^{A-4}+{ }_2 \mathrm{He}^4
\)
In \(\beta\)-decay, the mass number of product nucleus remains same but atomic number increases or decreases by one.
\(
{ }_z X^A \xrightarrow{\beta^{-} \text {decay }} { }_{Z+1}Y^A+{ }_{-1}^0 e+\nu
\)
\(
{ }_Z X^A \xrightarrow{\beta^{+} \text {decay }}{ }_{Z-1} Y^A+{ }_{+1}^0 e+\nu
\)
Gamma decay is the phenomenon of emission of gamma rays photon from a radioactive nucleus.
\(
{ }_z X^A \longrightarrow{ }_z X^A+\gamma
\)
Hence, the given reaction will have sequence as follows
\(
{ }_Z X^A \xrightarrow{\beta^{-} \text {emission }}{ }_{Z+1} Y^A \xrightarrow{\alpha \text {-emission }}{ }_{Z-1} K^{A-4} \xrightarrow{\gamma \text {-emission }}{ }_{Z-1} K^{A-4}
\)
The control rods used in a nuclear reactor can be made up of [Kerala CEE 2014]
(b) The control rods used in a nuclear reactor can be made up of cadmium. As they absorb fast moving neutrons.
The fusion reaction in the sun is a multi-step process in which the [Kerala CEE 2014]
(d) The fusion reaction in the sun is a multi-step process in which the hydrogen is burned into helium. Because in fusion, lighter nuclei combine to form heavier nucleus.
Explanation: The fusion reaction in the Sun involves the fusion of hydrogen nuclei (protons) to form helium nuclei. This process is a multi-step reaction, meaning it occurs in several stages. Ultimately, four hydrogen atoms are combined to create one helium atom, releasing a large amount of energy.Â
The nuclear fusion reaction between deuterium and tritium takes place [EAMCET 2014]
(b) The nuclear fusion is a very difficult process. Since, the nuclei to be fused are positively charged, they would repel one another strongly. Hence, they must be brought very close together not only by very high pressure but also with high kinetic energy ( \(\simeq 0.1 \mathrm{MeV}\) ). For this, a very high temperature of the order of \(10^8 \mathrm{~K}\) is required. Such high temperature are available in the sun and stars. On the earth, they may be produced by exploding a nuclear fission bomb.
A \(\mathrm{U}^{235}\) reactor generates power at a rate of \(P\) producing \(2 \times 10^{18}\) fission per second. The energy released per fission is 185 MeV. The value of \(P\) is [EAMCET 2013]
(a) Power, \(P=\frac{n E}{t}\)
Given, \(n=2 \times 10^{18}\) fission per second and \(E=185 \mathrm{MeV}\)
Here, \(\quad P=\frac{2 \times 10^{18} \times 185 \times 10^6 \mathrm{eV}}{1}\)
\(\Rightarrow \quad=2 \times 10^{18} \times 185 \times 10^6 \times 16 \times 10^{-19}=59.2 \mathrm{MW}\)
The purpose of using heavy water in nuclear reactor is [EAMCET 2013]
(d) To decrease the energy of fast neutrons to thermal energy.
Explanation: Heavy water is used in a nuclear reactor as a moderator, which means its primary function is to slow down the fast-moving neutrons produced during fission. These slow neutrons are more likely to interact with uranium-235 nuclei and cause further fission, thus sustaining the chain reaction.
The ratio of volumes of nuclei (assumed to be in spherical shape) with respective mass numbers 8 and 64 is [Kerala CET 2013]
(c) Nucleus of mass number \(A\) has a radius, \(R=R_0 A^{1 / 3}\) where, \(\quad R_0=1.2 \times 10^{-15} \mathrm{~m}\)
\(
\therefore \quad \frac{R_8}{R_{64}}=\left[\frac{8}{64}\right]^{1 / 3}=\left[\frac{1}{8}\right]^{1 / 3}
\)
\(\therefore\) Ratio of volume \(=\frac{1}{8}=0.125\)
Radioactivity of a sample at \(T_1\) time is \(R_1\) and at time \(T_2\) is \(R_2\). If half-life of sample is \(T\), then in time \(\left(T_2-T_1\right)\), the number of decayed atoms is proportional to [MP PMT 2013]
(b) Let \(R_1=N_1 \lambda\) and \(R_2=N_2 \lambda\)
Mean life, \(T=\frac{1}{\lambda}\)
\(
R_1-R_2=\left(N_1-N_2\right) \lambda=\left(N_1-N_2\right) \frac{1}{T}
\)
So, number of atoms disintegrated in ( \(T_2-T_1\) ) is
\(
=N_1-N_2=\left(R_1-R_2\right) T
\)
Which pair is isotonic?
\(
\text { (d) Since, } N=13-7=6, C=12-6=6
\)
Isotones are nuclides with the same number of neutrons.Â
Anlyzing options:
(a) \({ }_7 \mathrm{~N}^{13},{ }_7 \mathrm{~N}^{14}\) : Both have the same number of protons (7), but their neutron numbers differ ( 6 and 7 , respectively). Thus, they are not isotones.
(b) \({ }_6 \mathrm{C}^{14},{ }_6 \mathrm{C}^{12}\) : Both have the same number of protons (6), but their neutron numbers differ ( 8 and 6 , respectively). Thus, they are not isotones.
(c) \({ }_6 \mathrm{C}^{14},{ }_7 \mathrm{~N}^{14}\) : While both have a mass number of 14 , they have different numbers of protons ( 6 and 7 , respectively). Thus, they are not isotones.
(d) \({ }_7 \mathrm{~N}^{13},{ }_6 \mathrm{C}^{12}\) : Nitrogen-13 has 7 protons and 6 neutrons ( \(13-7=6\) ), and Carbon-12 has 6 protons and 6 neutrons \((12-6=6)\). They have the same number of neutrons (6), making them isotones.
Â
The phenomenon of radioactivity [UP CPMT 2013]
(c) is a nuclear process which does not depend on external forces.
Explanation
Radioactivity is a nuclear process: Radioactivity originates from the unstable nucleus of an atom, which undergoes spontaneous decay to become more stable.
Independence from external forces: The rate of radioactive decay is generally unaffected by external factors like temperature and pressure. This is because the forces within the nucleus (the strong nuclear force and electrostatic repulsion) that govern stability are not significantly influenced by these external conditions.
An atom bomb weighing 1 kg explodes releasing \(9 \times 10^{13} \mathrm{~J}\) of energy. What percentage of mass is converted into energy? [UP CPMT 2013]
\(
\begin{aligned}
&\text { (a) From, } E=(\Delta m) c^2\\
&\begin{array}{r}
\Delta m=\frac{E}{c^2}=\frac{9 \times 10^{13}}{\left(3 \times 10^8\right)^2}=10^{-3} \mathrm{~kg} \\
\therefore \frac{\Delta m}{m} \times 100=\frac{10^{-3}}{1} \times 100=0.1 \%
\end{array}
\end{aligned}
\)
Pick out the correct statements from the following.
I. Electron emission during \(\beta\)-decay is always accompanied by neutrons.
II. Nuclear force is charge independent.
III. Fusion is the chief source of stellar energy. [Karnataka CET 2013]
(d) We know that, nuclear forces are charge independent and the chief source of stellar energy is fusion.
\(\beta\)-decay is accompanied by both proton and neutron.
A nucleus \({ }_Z X^A\) emits an \(\alpha\)-particle with velocity \(v\). The recoil speed of the daughter nucleus is [Karnataka CET 2013]
\(
\text { (b) According to the question, }{ }_Z X^A \longrightarrow{ }_{Z-2} Y^{A-4}+{ }_2 \mathrm{He}^4
\)
Let the recoil speed of daughter nucleus is \(v^{\prime}\). By the law of conservation of momentum, we have
Initial momentum \(=\) Final momentum \(\Rightarrow 0=(A-4) v^{\prime}+4 v\)
\(
(A-4) v^{\prime}=-4 v \text { or } v^{\prime}=-\frac{4 v}{(A-4)}
\)
Here, negative sign shows that the recoil speed is in opposite direction to that of \(\alpha\)-particles.
A radioactive substance emits 100 beta particles in the first 2 s and 50 beta particles in the next 2 s. The mean life of the sample is [Karnataka CET 2013]
(c) Given, in 1st two seconds \(100 \beta\) particles and in next two seconds \(50 \beta\) particles are emitted.
\(
\therefore \quad T_{1 / 2}=2 \mathrm{~s}
\)
Hence, mean life, \(T=\frac{t_{1 / 2}}{0.693}=\frac{2}{0.693} \mathrm{~s}\)
When alpha particle captures an electron, then it becomes a [Kerala CET 2013]
(c) \(\alpha \text {-particle is He nucleus. Addition of an electron will change it into an ion. }\)
Explanation: An alpha particle is essentially a helium nucleus, consisting of two protons and two neutrons. It therefore carries a positive charge of +2 . When an alpha particle captures one electron, its charge changes from +2 to +1 . With a charge of +1 , but retaining its two protons, it becomes a singly ionized helium atom \(\left(\mathrm{He}^{+}\right)\)or, more simply, a helium ion.
The half-life of radioactive element is 600 yr. The fraction of sample that would remain after 3000 yr is [AIIMS 2012, Manipal 2012]
(d) We know that, \(n=\frac{t}{T}\) where, \(T=\) half-life.
Given,
\(
\begin{aligned}
t & =3000 \mathrm{yr} \\
T & =600 \mathrm{yr} \\
n & =\frac{3000}{600}=5 \\
\frac{N}{N_0} & =\left(\frac{1}{2}\right)^n \\
\frac{N}{N_0} & =\left(\frac{1}{2}\right)^5=\frac{1}{32}
\end{aligned}
\)
If a nucleus \({ }_Z X^A\) emits \(9 \alpha\) and \(5 \beta\)-particles, then the ratio of total protons and neutrons in the final nucleus is [BCECE Mains 2012]
(d) The given situation can be shown as
\(
{ }_Z X^A \xrightarrow{9 \alpha}{ }_{Z-18} X^{A-36} \xrightarrow{5 \beta}{ }_{Z-13} X^{A-36}
\)
\(\therefore \quad\) Number of protons, \(P=(Z-13)\) and number of neutrons,
\(
\begin{aligned}
& & N & =(A-36)-(Z-13)=(A-Z-23) \\
\therefore & & \frac{P}{N} & =\frac{(Z-13)}{(A-Z-23)}
\end{aligned}
\)
If the half-life of a material is 10 yr, then in what time, it becomes \(\frac{1}{4}\) th part of the initial amount? [BCECE Mains 2012]
\(
\begin{aligned}
&\text { (b) We know that, } N=N_0\left(\frac{1}{2}\right)^{\frac{t}{T_{1 / 2}}}\\
&\frac{1}{4}=\left(\frac{1}{2}\right) \Rightarrow\left(\frac{1}{2}\right)^{\frac{t}{10}}=\left(\frac{1}{2}\right)^2 \Rightarrow t=20 \mathrm{yr}
\end{aligned}
\)
What is the \(Q\)-value of the reaction?
\(
{ }^1 \mathrm{H}+{ }^7 \mathrm{Li} \longrightarrow{ }^4 \mathrm{He}+{ }^4 \mathrm{He}
\)
The atomic masses of \({ }^1 \mathrm{H},{ }^4 \mathrm{He}\) and \({ }^7 \mathrm{Li}\) are \(1.0078254 \mathrm{u}, 4.0026034 \mathrm{u}\) and 7.016004 u , respectively. [Manipal 2012]
(a) The total mass of the initial particles,
\(
m_i=1.007825+7.016004=8.023829 \mathrm{u}
\)
and the total mass of final particles,
\(
m_f=2 \times 4.002603=8.005206 \mathrm{u}
\)
Difference between initial and final mass of particles,
\(
\Delta m=m_i-m_f=8.023829-8.005206=0.018623 \mathrm{u}
\)
The \(Q\)-value is given by
\(
Q=(\Delta m) c^2=0.018623 \times 931.5=17.35 \mathrm{MeV}
\)
A nucleus of mass number 220, initially at rest, emits an \(\alpha\)-particle. If the \(Q\)-value of the reaction is 5.5 MeV, then the energy of the emitted \(\alpha\)-particle will be [AMU 2012]
(b)
\(Q\)-value of the reaction is 5.5 MeV .
i.e. \(\quad K_1+K_2=5.5 \mathrm{MeV} \dots(i)\)
By conservation of linear momentum, \(p_1=p_2\)
\(
\begin{aligned}
\Rightarrow \sqrt{2(216) K_1} & =\sqrt{2(4) K_2} \\
K_2 & =54 K_1 \dots(ii)
\end{aligned}
\)
On solving Eqs. (i) and (ii), we get
The energy of emitted \(\boldsymbol{\alpha}\)-particle, \(K_2=5.4 \mathrm{MeV}\)
A radioactive substance emits \(n\) beta particles in the first 2 s and \(0.5 n\) beta particles in the next 2 s. The mean life of the sample is [AMU 2012]
(c) We have, \(\lambda=\frac{0.693}{T_{1 / 2}}[latex] Mean life, [latex]\tau=\frac{1}{\lambda}=\frac{t_{1 / 2}}{0.693}=\frac{2}{2.303 \log 2}=\frac{2}{\ln 2} \mathrm{~s}\)
A luminous body radiates energy at a rate \(3.6 \times 10^{28} \mathrm{~J} / \mathrm{s}\), then loss of the mass of the body per second is [OJEE 2011]
(c) Energy and mass are related by the relation, \(E=m c^2\)
Differentiating, we get
\(
\begin{gathered}
\frac{d E}{d t}=m \times[0]+c^2 \frac{d m}{d t} \\
\Rightarrow \quad 3.6 \times 10^{28}=9 \times 10^{16} \frac{d m}{d t} \Rightarrow \frac{d m}{d t}=4 \times 10^{11} \mathrm{~kg} / \mathrm{s}
\end{gathered}
\)
The disintegration rate of a certain radioactive sample at any instant is 5400 disintegrations per minute and 5 min later, the rate becomes 600 disintegrations per minute. Half-life of sample is [EAMCET 2011]
(c) From the relation, \(R=R_0 e^{-\lambda t}\) (where, \(R=\) activity of sample)
Given, \(R_0=5400 \mathrm{dis} / \mathrm{min}\)
\(
\begin{aligned}
R & =600 \mathrm{dis} / \mathrm{min} \text { and } t=5 \mathrm{~min} \\
\therefore \quad 600 & =5400 e^{-5 \lambda} \\
\frac{1}{9} & =e^{-5 \lambda} \Rightarrow \lambda=\frac{\ln 9}{5}
\end{aligned}
\)
\(\therefore\) Half-life of the sample, \(T_{1 / 2}=\frac{\ln 2}{\frac{\ln 9}{5}}=\frac{5 \ln 2}{\ln 9}=\frac{\ln 2^5}{\ln 9}=\frac{\ln 32}{\ln 9}\)
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