Adjoint gamma ray estimation to the surface of a cylinder: analysis of a remote reprocessng facility

Technical Report · Wed Jul 01 00:00:00 EDT 1981

DOI:https://doi.org/10.2172/6412139· OSTI ID:6412139

Cramer, S. N.

The next event estimator in the MORSE multigroup Monte Carlo code has been extended to include Klein-Nishina scattering and annihilation radiation from pair production for both the forward and adjoint modes of calculation. A formulation for the solid angle subtended at a point by a cylinder has also been used in the estimator. These procedures have been included in the investigation of the gamma ray environment in the design of a remote fuel reprocessing facility. Calculational results are presented which indicate the validity and efficiency of the developed methods as compared to those in standard use.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6412139
• Report Number(s): ORNL/TM-7686; ON: DE81027673; TRN: 81-013714
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
FUEL REPROCESSING PLANTS
GAMMA RADIATION
FORECASTING
ADJOINT DIFFERENCE METHOD
ADJOINT FLUX
CYLINDERS
MONTE CARLO METHOD
MULTIGROUP THEORY
RADIATION DOSES
REMOTE CONTROL
SAMPLERS
CONTROL
DOSES
ELECTROMAGNETIC RADIATION
EQUIPMENT
IONIZING RADIATIONS
LABORATORY EQUIPMENT
NEUTRON FLUX
NEUTRON TRANSPORT THEORY
NUCLEAR FACILITIES
RADIATION FLUX
RADIATIONS
TRANSPORT THEORY
050800* - Nuclear Fuels- Spent Fuels Reprocessing
054000 - Nuclear Fuels- Health & Safety