Solve your IGNOU Doubts
Solve your IGNOU Doubts
Question:

Write two-group criticality condition for a bare homogeneous reactor. Using this equation, show that the six factor criticality condition for two group theory is given by nf pequation pf pt =1.symbols have their usual meanings.

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Question:

The scattering cross-section of Carbon at 1 eV is 4.8 barn. Estimate the diffusion coefficient of Carbon. Assume that a is almost negligible.

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Question:

For an arbitrary volume V of material in which one speed neutrons interacts with medium nuclei, if n(r,t)  is the neutron density at r  and at time t , obtain the equation of continuity. Also, obtain equation for steady state.

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Question:

Discuss the initial, boundary and source conditions

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Question:

Using spherical harmonics method for a non- multiplying 1-D plane geometry, write the exact infinite coupled equations. Hence for a large non-absorbing system, obtain equations under P1 approximation. Discuss the limitations of PN approximation

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Question:

Write the basic assumptions made to derive the transport equation. Hence, derive the Boltzmann transport equation for a multiplying system in terms of neutron flux.

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Question:

Define angular neutron flux and angular current density. The neutron flux at a particular location in a reactor core is  1x1014 neutrons cm- 2s-1What is the average density (in neutrons cm-3 ) 3 in of the thermal neutrons at the same location in the core?

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Question:

If a 10 MeV neutron is collided with 238 U nuclide, compare the average energy loss of neuron if they undergo a) inelastic scattering and b) elastic scattering.

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Question:

Derive an expression of average logarithmic energy decrement per collision (). Hence, show that for large mass number, it is independent of energy. Using this formula, plot average logarithmic energy decrement for different nuclides of mass number A.

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Question:

A 2.6 MeV neutron collides with hydrogen. Calculate the probability that the energy of neutron is within the energy range 0.63 and 0.75 MeV after collision? If a neutron loses 0.75 MeV in LAB system, what is the scattering angle in the CM system?

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Question:

Define LAB and CM coordinate frames of reference used to study the kinematics of two- body collision. Obtain an expression of kinetic energy of a neutron after collision in the LAB system.

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Question:

Discuss the concept of breeding and doubling time and describe how abundant fertile actinides could be converted to excellent fissile actinides.

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Question:

i) What is the difference between slowing down density and flux of neutrons? 

ii) If the reference neutron energy is 10 MeV, calculate the lethargy at 200 keV, and 0.025 eV?

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Question:

The average number of neutrons produced per fission is 2.5. What would happen in a second, if every neutron released in fission causes another fission? Assume a generation time of 0.1 second.

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Question:

Distinguish between prompt and delayed neutrons released in fission and discuss their importance.

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Question:

Calculate the macroscopic scattering cross section for natural uranium. Given 3   18.9 g/cm , percentage weight of 235U in natural uranium is 0.713; the rest being 238U . The scattering cross sections for 235U and 238U isotopes being 15 b and 13.8 b, respectively.

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Question:

पर्यटन में संयुक्त प्रचार-प्रसार करना क्यों आवश्यक है?

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Question:

बहुविषयक दृष्टिकोण क्या है?

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Question:

ज्ञानानुशासन कैसे विकसित होता है?

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Question:

 

"क्राइस्टोलॉजी" से आपका क्या तात्पर्य है?

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