Introduction To Health Physics
Introduction To Health Physics
5th Edition
ISBN: 9780071835275
Author: Johnson, Thomas E. (thomas Edward), Cember, Herman.
Publisher: Mcgraw-hill Education,
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Chapter 5, Problem 5.37P

(a)

To determine

The microscopic cross- section for N and O for thermal neutrons.

(b)

To determine

The scattering means free path of thermal neutron.

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A swimming pool reactor produces a flux of 3x1016 thermal neutrons m-2 s-1 at 1 m from the reactor center. Assuming a parallel beam of neutrons diffusing up to the surface of the pool where the neutron flux is measured to be 108 m -2 s-1. Calculate the thickness ( x m) of the water layer required. For thermal neutrons the flux is reduced exponentially with the experiment x L-1 where L is the diffusion length ( 2.75 cm in H2O).
Control rods are usually made of an alloy of indium. The absorption cross-section of indium for thermal neutron is 71 b, and the mass density of solid indium is 7.31 g cm-3. Estimate the neutron transmission ratio of a 1-cm thick indium slab. (a) 0.07 (b)0.7 (c) 0.01 (d) 0.1
A point source of thermal neutrons is placed at the centre of a large sphere of beryllium. Deduce the spatial distribution of neutron density in the sphere. Estimate what its radius must be if less than 1% of the neutrons are to escape through the surface. Find also the neutron density near the surface in this case in terms of the source strength. At. Wt of beryllium = 9 Density of beryllium = 1.85 g/cc Avagadro number = 6 x 1023 atoms/g atom Thermal neutron scattering cross-section on beryllium = 5.6 barns Thermal neutron capture cross-section on beryllium 10 mb (at velocity v = 2,200 m/s) =
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