IGNOU MPHE 26 SOLVED ASSIGNMENT

Ques 1.

 Calculate, using Weiszäcker formula, the binding energy per nucleon for .
Given: 

Ques 2.

 Define reaction rate. Write its mathematical formula. Explain each term involves in it. 

Ques 3.

Differentiate between neutron elastic scattering and inelastic scattering. Draw elastic scattering cross-section curves for  and  and write their features. 

Ques 4.

What are prompt and delayed neutrons? Discuss the role of delayed neutrons in reactor safety.

Ques 5.

Draw and explain the energy variation of fission cross-sections for  and . 

Ques 6.

Derive the four factor formula and explain each term involves in it with mathematical steps. Hence, obtain six-factor formula. 

Ques 7.

Show that the average cosine of scattering angle in the LAB system () is given by , where A is the mass number of nucleus. Is this relation applies to hydrogen? 

Ques 8.

The initial energy of a neutron is 2 MeV, calculate the maximum energy loss due to elastic scattering in . 

Ques 9.

 Describe the Fermi-age theory and derive Fermi-age approximation of slowing down equation for a weak absorbing medium. Discuss the S-G approximation. 

Ques 10.

 5 MeV neutron is scattered through an angle of 45 degrees in a collision with  nucleus. Calculate the energy of scattered neutrons and energy of the recoiling nucleus. 

Ques 11.

 Derive neutron transport equation in terms of angular neutron flux for a heterogeneous multiplying assembly. Rewrite simplified form of this equation for a non-multiplying and homogeneous assembly.

Ques 12.

 What are

Ques 13.

What are (i) initial and boundary conditions, and (ii) Interface boundary conditions?

Ques 14.

Using the transport equation for a non-multiplying system and homogeneous assembly, derive the integral form of transport equation using the method of characteristics. What do you understand by "Optical path length" of the medium?

Ques 15.

What do you understand by constant cross-section approximation? Derive the steady state equation for a plane geometry. Also write the transport equation for a spherical geometry.

Ques 16.

Starting with the general form of transport equation, obtain the diffusion equation
$

Ques 17.

State Fick's law. Discuss its importance in neutron transport /diffusion. Write the assumptions used to derive Fick's law and hence derive its expression.

Ques 18.

Derive two-group diffusion equations for a critical homogeneous reactor in steady state.

Ques 19.

 Show that the root mean square crow-flight distance for neutrons from an infinite plane source in an infinite medium is .

Ques 20.

 Calculate, using Weiszäcker formula, the binding energy per nucleon for .
Given: 

Ques 21.

 Define reaction rate. Write its mathematical formula. Explain each term involves in it. 

Ques 22.

Differentiate between neutron elastic scattering and inelastic scattering. Draw elastic scattering cross-section curves for  and  and write their features. 

Ques 23.

What are prompt and delayed neutrons? Discuss the role of delayed neutrons in reactor safety.

Ques 24.

Draw and explain the energy variation of fission cross-sections for  and . 

Ques 25.

Derive the four factor formula and explain each term involves in it with mathematical steps. Hence, obtain six-factor formula. 

Ques 26.

Show that the average cosine of scattering angle in the LAB system () is given by , where A is the mass number of nucleus. Is this relation applies to hydrogen? 

Ques 27.

The initial energy of a neutron is 2 MeV, calculate the maximum energy loss due to elastic scattering in . 

Ques 28.

 Describe the Fermi-age theory and derive Fermi-age approximation of slowing down equation for a weak absorbing medium. Discuss the S-G approximation. 

Ques 29.

 5 MeV neutron is scattered through an angle of 45 degrees in a collision with  nucleus. Calculate the energy of scattered neutrons and energy of the recoiling nucleus. 

Ques 30.

 Derive neutron transport equation in terms of angular neutron flux for a heterogeneous multiplying assembly. Rewrite simplified form of this equation for a non-multiplying and homogeneous assembly.

Ques 31.

 What are

Ques 32.

What are (i) initial and boundary conditions, and (ii) Interface boundary conditions?

Ques 33.

Using the transport equation for a non-multiplying system and homogeneous assembly, derive the integral form of transport equation using the method of characteristics. What do you understand by "Optical path length" of the medium?

Ques 34.

What do you understand by constant cross-section approximation? Derive the steady state equation for a plane geometry. Also write the transport equation for a spherical geometry.

Ques 35.

Starting with the general form of transport equation, obtain the diffusion equation
$

Ques 36.

State Fick's law. Discuss its importance in neutron transport /diffusion. Write the assumptions used to derive Fick's law and hence derive its expression.

Ques 37.

Derive two-group diffusion equations for a critical homogeneous reactor in steady state.

Ques 38.

 Show that the root mean square crow-flight distance for neutrons from an infinite plane source in an infinite medium is .

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