8.2 Problems 445barns for a neutron velocityv= 2 ,200 m/s. If the counting rate is 250/min,
calculate the value ofQ.GivenL=50 cm;D= 5 × 105 cm^2 /s.
[University of Bristol 1959]
8.79 Calculate the thermal utilization factor for a heterogeneous lattice made up of
cylindrical uranium rods of diameter 3 cm and pitch 18 cm in graphite
Take the flux ratioφm/φUas 1.6
Densities : Uranium= 18. 7 × 103 kg m−^3 , Graphite= 1. 62 × 103 kg m−^3
Absorption cross-sectionsσav= 7 .68 b;σam= 4. 5 × 10 −^3 b.
[University of Durham 1961]
8.80 Calculate approximately, using one-group theory results, the critical size of a
bare spherical reactor, givenk∞= 1 .54 and Migration areaM^2 =250 cm^2.8.81 Assuming the energy released per fission of^235 U is 200 MeV, calculate the
amount of^235 U consumed per day in Canada India reactor “Cirus” operating
at 40 MW of power.
8.82 Assuming that the energy released per fission of^23592 U is 200 MeV, calculate the
number of fission processes that should occur per second in a nuclear reactor
to operate at a power level of 20,000 kW. What is the corresponding rate of
consumption of^23592 U.
[University of London 1959]
8.83 (a) Assume that in each fission of^235 U, 200 MeV is released. Assuming that
5% of the energy is wasted in neutrinos, calculate the amount of^235 U
burned which would be necessary to supply at 30% efficiency, the whole
annual electricity consumption in Britain 50× 109 kWh
(b) A thermal reactor contains 100 tons of natural uranium (density 19) and
operates at a power of 100 MW (heat). Assuming that the thermal cross-
section of^235 U is 550 barns and that the uranium contains 0.7 % of^235 U.
Calculate the neutron flux near the centre of the reactor by neglecting neu-
tron losses from the outside, and assuming flux constant through out the
lattice.
[University of Liverpool 1959]
8.84 If the elastic scattering of neutrons by hydrogen nuclei is isotropic in the centre
of mass system, show that
ln(E 1 /E 2 )= 1whereE 1 andE 2 are respectively the kinetic energies of a neutron before and
after the collision.
[University of London 1969]
8.85 (a) Estimate the average number of collisions required to reduce fast fission
neutrons of initial energy 2 MeV to thermal energy (0.025 eV) in graphite
moderator.
(b) Calculate the corresponding slowing-down time given thatΣs= 0 .385 cm−^1