A Reactor Pressure Vessel Dosimetry Calculation Using ATTILA, An Unstructured Tetrahedral Mesh Discrete-Ordinates Code

Conference · Wed Dec 31 00:00:00 EST 1997

OSTI ID:626463

Wareing, T A; Parsons, D K ^[1]; Pautz, S ^[2]

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1. Los Alamos National Lab., NM (United States)
2. Texas A and M Univ., College Station, TX (United States). Dept. of Nuclear Engineering

Recently, a new state-of-the-art discrete-ordinates code, ATTILA, was developed. ATTILA provides the capabilities to solve geometrically complex 3-D transport problems by using an unstructured tetrahedral mesh. In this paper we describe the application of ATTILA to a 3-D reactor pressure vessel dosimetry problem. We provide numerical results from ATTILA and the Monte Carlo code, MCNP. The results demonstrate the effectiveness and efficiency of ATTILA for such calculations.

• Research Organization: Los Alamos National Lab., NM (United States).
• Sponsoring Organization: USDOE Assistant Secretary for Management and Administration, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 626463
• Report Number(s): LA-UR-97-2268; CONF-971005-; ON: DE97008629; TRN: 98:006942
• Resource Relation: Conference: Joint international conference on mathematical methods and supercomputing in nuclear applications, Saratoga Springs, NY (United States), 6-10 Oct 1997; Other Information: PBD: 1997
• Country of Publication: United States
• Language: English

Related Subjects

99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
MONTE CARLO METHOD
PRESSURE VESSELS
FAST NEUTRONS
DOSIMETRY
COMPUTER CODES
IRRADIATION