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nuclear physics

Questions and Answers of Nuclear Physics

The events (1) loss of offsite power, (2) Coolant pumps, (3) Steam water system, and (4) Transients] contribute to core damage frequency (CDF). Given a core damage event, calculate the probability
Suppose that the strength of a material is a linear function of two variables \(X\) and \(Y\), as \(S=a X+b Y\). The variables \(X\) and \(Y\) are normally distributed with mean \(\mu_{X}\) and
Consider a \(\mathrm{BF}_{3}\) neutron detector of length \(20 \mathrm{~cm}\). Find its efficiency for thermal \((0.025 \mathrm{eV})\) and fast \((1 \mathrm{MeV})\) neutrons. Assume the fill gas
Using the Maxwell distribution for neutron flux given in Eq. (10.4), establish the relation between average energy and peak energy. Also, find the value of temperature that would correspond to a peak
Using the value of constants, \(A=1.058 \times 10^{3}, B=1.0363\), and \(C=2.29\), in Eq. (10.6), obtain the plot of Watt spectrum for neutron induced fission in \({ }^{235} \mathrm{U}\). N(E)=Ae=BE
Find the saturation activity induced in gold foil irradiated in a thermal neutron flux of \(1.0 \times 10^{9} \mathrm{n} / \mathrm{cm}^{2} / \mathrm{s}\), given that the activation cross section for
Assume a copper foil to be irradiated in a thermal neutron flux of \(1.0 \times 10^{9} \mathrm{n} / \mathrm{cm}^{2} / \mathrm{s}\). Using activation cross section for \({ }^{63} \mathrm{Cu}\) as
Assuming detector efficiency of \(2 \%\), find the counts recorded by the detector for a gold foil irradiated in a thermal flux of \(1.0 \times 10^{9} \mathrm{n} / \mathrm{cm}^{2} / \mathrm{s}\) for
On insertion of a certain positive reactivity into a critical reactor (fueled with \({ }^{235} \mathrm{U}\) ), power was found to double every \(600 \mathrm{~s}\). Find the associated reactor period
A positive reactivity was added to a critical reactor operating at a certain steady power level. The reactor power increased by \(20 \%\) in \(100 \mathrm{~s}\). Use the delayed neutron data given in
A critical reactor is operating at power of \(100 \mathrm{~W}\) and a certain amount of instantaneous negative reactivity is added into the core. Immediately after reactivity addition, the power
A critical reactor is operating at \(100 \mathrm{~W}\) power and \(90 \mathrm{mK}\) of instantaneous negative reactivity is added into the core. Find the power level immediately after the reactivity
In a certain subcritical measurement, the detector counts observed between two successive reactivity insertion stages were \(3450 \mathrm{cps}\) and \(4675 \mathrm{cps}\). Find the level of
(a) In experimental reactors, the control rod worth is measured using the change in geometric buckling. Assuming that only the leakage or geometrical buckling changes in such an experiment, derive an
Calculate and compare the ranges of alpha of energy \(4.5 \mathrm{MeV}\) and beta particle of energy \(0.6 \mathrm{MeV}\) in polyethylene and acrylic glass. Use Bragg-Kleeman relation in the case of
For a gamma photon of energy \(1.5 \mathrm{MeV}\), calculate the maximum and minimum energy loss as a result of Compton scattering.
The mass attenuation coefficients for gamma radiation of energy \(5 \mathrm{MeV}\) in sodium, iron, and lead are \(2.753 \mathrm{E}-02,3.146 \mathrm{E}-02\), and \(4.272 \mathrm{E}-02 \mathrm{~g} /
Assume that \(5 \mathrm{MeV}\) gamma (in the form of a narrow beam) is incident on a composite medium of \(2 \mathrm{~cm}\) sodium, \(0.5 \mathrm{~cm}\) of lead, and some unknown thickness of Iron
Consider that a monoenergetic point source of gamma radiation \((800 \mathrm{keV})\) with strength of \(10^{5}\) gammas \(/ \mathrm{s}\) is located at a point in air. At a distance of \(5
If the half value layer for iron is \(1.7 \mathrm{~cm}\) for \(1.332 \mathrm{MeV}\) photons and the exposure rate from a source is \(1000 \mathrm{mR} / \mathrm{h}\), calculate (a)
Compute the following reaction rates \(/ \mathrm{cm}^{3} / \mathrm{s}\) :a. B-10(n, \(\alpha) \mathrm{Li}-7\) in the material Boron Carbide \(\mathrm{B}_{4} \mathrm{C}\) of density \(2.3 \mathrm{~g}
Consider a line source of length \(50 \mathrm{~cm}\) and with strength of \(10^{4}\) gammas \(/ \mathrm{cm} / \mathrm{s}\) and surrounded by vacuum. It emits two gammas of energy 200 and \(1250
A cesium source in the form of a disc of radius \(3 \mathrm{~cm}\) has a uniform activity of strength \(2 \mathrm{mCi} / \mathrm{cm}^{2}\). What is the dose at a point \(\mathrm{P}, 10 \mathrm{~cm}\)
A point source of photons of energy \(1.0 \mathrm{MeV}\) is giving a dose of \(10 \mathrm{mR} / \mathrm{h}\) at a dose point \(P\). How much thickness of lead (density \(11 \mathrm{~g} /
Calculate the dpa that iron experiences when iron is exposed to a \(1 \mathrm{MeV}\) neutron flux of \(5 \times 10^{15} / \mathrm{cm}^{2} / \mathrm{s}\) for a period of 2 years. Take the damage
What are the new features of Gen III/ \(\mathrm{III}^{+}\)reactors relative to the Gen I and Gen II reactors?
What are the features that foster to innovate over Gen \(\mathrm{III} / \mathrm{III}^{+}\)reactors and what new goals are specified for Gen IV reactors?
The challenges arising in designing the reactor with core outlet temperature of the order of \(1273 \mathrm{~K}\) ?
What are the common and unique features of six types of Gen IV reactors?
The fuel invented to withstand high temperature in HTRs and its special characteristics?
Explain the configurations in vogue in the design of HTRs.
Advantages of heavy metal-cooled fast reactors and helium gas-cooled fast reactors over sodium-cooled fast reactors?
Advantages and challenges in developing the molten salt reactors?
Challenges in the design of super critical water reactors?
What are the objectives of developing HTRs and MSR in India?
List the reactor physics design challenges in Gen IV reactors?
List the major incentives in developing SMRs.
The goals to be achieved by SMR design?
The applications of nonelectric power generation in nuclear reactors in different types of industry?
Major change in the design of light and heavy water reactors to achieve design characteristics of SMRs.
Explain inherent safety and passive safety in the reactors.
How the cost, safety, waste generation, and proliferation of resistance of SMRs can be compared with large-sized reactors.
List the design features that are affected by the "size" and the "design" of the SMRs?
What is Breeder and Burn (B\&B) concept?
The genesis of TWRs and the mechanism that establishes the TWRs?
The parameters that characterize the TWRs?
What are the necessary conditions for development of TWRs, SWRs, CANDLE, and UCB SWRs?
What way the TWRs are different than the SWRs?
What are the reactor physics requirements for sustainability of TWRs?
What is the strategy of fuel utilization in a CANDLE reactor?
What are the advantages of CANDLE reactors?
Major challenges in developing B\&B concept based reactors?

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