Shielding Analyses: The Rabbit vs the Turtle?

Conference · Sun Apr 21 00:00:00 EDT 1996

OSTI ID:459315

Broadhead, B. L. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division

This paper compares solutions using Monte Carlo and discrete- ordinates methods applied to two actual shielding situations in order to make some general observations concerning the efficiency and advantages/disadvantages of the two approaches. The discrete- ordinates solutions are performed using two-dimensional geometries, while the Monte Carlo approaches utilize three-dimensional geometries with both multigroup and point cross-section data.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 459315
• Report Number(s): CONF-960415-43; ON: DE97002972; TRN: 97:006724
• Resource Relation: Conference: American Nuclear Society (ANS) Radiation Protection and Shielding Division Topical Meeting on Advancements and Applications in Radiation Protection and Shielding , Falmouth, MA (United States), 21-25 Apr 1996; Other Information: PBD: [1996]
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICS AND COMPUTING
SHIELDING
D CODES
S CODES
M CODES
COMPARATIVE EVALUATIONS
GAMMA RADIATION
NEUTRONS
MONTE CARLO METHOD
DISCRETE ORDINATE METHOD
NEUTRON TRANSPORT
TWO-DIMENSIONAL CALCULATIONS
THREE-DIMENSIONAL CALCULATIONS
CRITICALITY
ALARM SYSTEMS
SAFETY
SPENT FUELS
SPENT FUEL CASKS
RADIATION DOSES
Nuclear Criticality Safety Program (NCSP)
Monte Carlo Methods
Criticality Accident Alarm System (CAAS)
DORT
Pressurized Water Reactor (PWR)
Spent Fuel Assemblies
Point-Cross-Section Libraries