1. List and describe any or all of the 5 neutron
source mechanisms
from Lesson 12.
2. Calculate the neutron source due to spontaneous fission
and/or 
emission. (This includes both the yield and
multigroup
spectrum, with appropriate information provided.)
3. List and describe any or all of the 7 gamma ray source
mechanisms
from Lesson 13.
4. Calculate the gamma rays source (yield and energy
distribution) from
fission and radioactive sources.
5. Describe the multigroup energy representation and coupled
multigroup
cross sections.
6. Define and discuss any of the terms defined in Lesson 14
and 15.
7. Define the response function.
8. Compute neutron response functions for elastic and
inelastic neutron
scattering.
9. Compute the photon response function, either using 
for
kerma or other variations on 
based on what is included in the flux calculation (i.e., like Cases 1
through
4 on pp. 142-144 in text).
10. Distinguish between free-field and local flux response
functions.
11. Distinguish between simple and anthropomorphic phantoms,
including
the differences, depth variations, and irradiation geometries discussed
in Lesson 19.
12. Be able to derive the UNATTENUATED dose equations for
line, disk, or volumetric slab sources. (Text Eqns. 6.26, 6.36,
or 6.56). For the slab source, I would give you Eqn. 6.43.
13. Be able to work a problem to find the total dose for a
shielded point source, including buildup (using the single-term Taylor
form with Table 7.2 provided to you).
14. Be able to work problems like any of the homework problems.
90% of the points on the test will be from the above
items. The
other 10% will be creative application of concepts from the material.
NE406 Radiation Protection and Shielding