Response matrix Monte Carlo based on a general geometry local calculation for electron transport

Conference · Tue Jan 01 04:00:00 EST 1991

OSTI ID:6245674

Ballinger, C T; Rathkopf, J A ^[1]; Martin, W R ^[2]

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1. Lawrence Livermore National Lab., CA (USA)
2. Michigan Univ., Ann Arbor, MI (USA). Dept. of Nuclear Engineering

A Response Matrix Monte Carlo (RMMC) method has been developed for solving electron transport problems. This method was born of the need to have a reliable, computationally efficient transport method for low energy electrons (below a few hundred keV) in all materials. Today, condensed history methods are used which reduce the computation time by modeling the combined effect of many collisions but fail at low energy because of the assumptions required to characterize the electron scattering. Analog Monte Carlo simulations are prohibitively expensive since electrons undergo coulombic scattering with little state change after a collision. The RMMC method attempts to combine the accuracy of an analog Monte Carlo simulation with the speed of the condensed history methods. Like condensed history, the RMMC method uses probability distributions functions (PDFs) to describe the energy and direction of the electron after several collisions. However, unlike the condensed history method the PDFs are based on an analog Monte Carlo simulation over a small region. Condensed history theories require assumptions about the electron scattering to derive the PDFs for direction and energy. Thus the RMMC method samples from PDFs which more accurately represent the electron random walk. Results show good agreement between the RMMC method and analog Monte Carlo. 13 refs., 8 figs.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6245674
• Report Number(s): UCRL-JC-105626; CONF-910414--19; ON: DE91007638
• Country of Publication: United States
• Language: English

Related Subjects

654001* -- Radiation & Shielding Physics-- Radiation Physics
Shielding Calculations & Experiments
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
CHARGED-PARTICLE TRANSPORT
CROSS SECTIONS
DISTRIBUTION FUNCTIONS
EQUATIONS
FUNCTIONS
MONTE CARLO METHOD
RADIATION TRANSPORT
REACTOR KINETICS EQUATIONS
RESPONSE MATRIX METHOD
SCATTERING