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USE OF THE MORSE MONTE CARLO CODE TO SOLVE SHIELDING AND CRITICALITY PROBLEMS OF SPENT FUEL CASKS.

Technical Report ·
OSTI ID:4626680
; ;
Research Organization:
Oak Ridge National Lab., Tenn.); (Division of Materials Licensing (AEC), Washington, D. C.; Science Applications, Inc., Huntsville, Ala. (USA)
NSA Number:
NSA-26-039025
OSTI ID:
4626680
Report Number(s):
CONF-720607--9
Country of Publication:
Country unknown/Code not available
Language:
English

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USE OF THE MORSE MONTE CARLO CODE TO SOLVE SHIELDING AND CRITICALITY PROBLEMS OF SPENT FUEL CASKS.
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CAPABILITIES OF THE MORSE MULTIGROUP MONTE CARLO CODE IN SOLVING REACTOR EIGENVALUE PROBLEMS.
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Related Subjects

CASKS
COMPUTER PROGRAMS/MORSE
for calculation of spent fuel container criticality
CRITICALITY
M CODES
MONTE CARLO METHOD
N52300 --Nuclear Materials & Waste Management--Handling Equipment & Procedures
N52420* --Nuclear Materials & Waste Management-- Transportation--Containers
NUMERICAL SOLUTION
REACTOR FUEL ELEMENTS/shipping of spent
criticality calculations for depleted uranium container for
SHIELDED CONTAINERS/criticality of spent fuel shipping
MORSE Monte Carlo Transport code for calculation of
SPENT FUELS
TRANSPORT THEORY