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?
### Definitions 1. Angular Neutron Flux (\(\phi(\mathbf{r}, \mathbf{\Omega}, E)\)): The number of neutrons passing through a unit area per unit time, traveling in a specific direction (\(\mathbf{\Omega}\)) with a specific energy (\(E\)). It is given as: \[ \phi(\mathbf{r}, \mathbf{\Omega}, E) = _______ _______ _________ _______ _______ ___ ______ ____ ________ ________ ____.
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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.
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 p pf pt =1.symbols have their usual meanings.
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.
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?
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?
Distinguish between prompt and delayed neutrons released in fission and discuss their importance.
Discuss the concept of breeding and doubling time and describe how abundant fertile actinides could be converted to excellent fissile actinides.