USE OF THE MORSE MONTE CARLO CODE TO SOLVE SHIELDING AND CRITICALITY PROBLEMS OF SPENT FUEL CASKS.
Journal Article
·
· Trans. Amer. Nucl. Soc. 15: No. 1, 547-8(Jun 1972).
OSTI ID:4698600
- Research Organization:
- Oak Ridge National Lab., Tenn.
- NSA Number:
- NSA-26-044510
- OSTI ID:
- 4698600
- Journal Information:
- Trans. Amer. Nucl. Soc. 15: No. 1, 547-8(Jun 1972)., Journal Name: Trans. Amer. Nucl. Soc. 15: No. 1, 547-8(Jun 1972).; ISSN TANSA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
USE OF THE MORSE MONTE CARLO CODE TO SOLVE SHIELDING AND CRITICALITY PROBLEMS OF SPENT FUEL CASKS.
CAPABILITIES OF THE MORSE MULTIGROUP MONTE CARLO CODE IN SOLVING REACTOR EIGENVALUE PROBLEMS.
Validity of the Monte Carlo method for shielding analysis of a spent-fuel shipping cask: comparison with experiment
Technical Report
·
Mon Oct 30 23:00:00 EST 1972
·
OSTI ID:4626680
CAPABILITIES OF THE MORSE MULTIGROUP MONTE CARLO CODE IN SOLVING REACTOR EIGENVALUE PROBLEMS.
Technical Report
·
Thu Dec 31 23:00:00 EST 1970
·
OSTI ID:4705927
Validity of the Monte Carlo method for shielding analysis of a spent-fuel shipping cask: comparison with experiment
Journal Article
·
Fri Jul 01 00:00:00 EDT 1983
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:5735176
Related Subjects
CONTAINERS
CRITICALITY
FUEL ELEMENTS
M CODES
MONTE CARLO METHOD
N72400* --Physics (Radiation & Shielding)--Shielding Calculations & Experiments
REACTOR FUEL ELEMENTS/criticality problems of spent
use of Morse Monte Carlo code to solve
(T)
REACTOR FUEL ELEMENTS/shielding problems of spent
use of Morse Monte Carlo code to solve
(T)
SHIELDING
CRITICALITY
FUEL ELEMENTS
M CODES
MONTE CARLO METHOD
N72400* --Physics (Radiation & Shielding)--Shielding Calculations & Experiments
REACTOR FUEL ELEMENTS/criticality problems of spent
use of Morse Monte Carlo code to solve
(T)
REACTOR FUEL ELEMENTS/shielding problems of spent
use of Morse Monte Carlo code to solve
(T)
SHIELDING