Published 1997
| Version v1
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A Reactor Pressure Vessel Dosimetry Calculation Using ATTILA, An Unstructured Tetrahedral Mesh Discrete-Ordinates Code
Creators
- 1. Los Alamos National Lab., NM (United States)
- 2. Texas A and M Univ., College Station, TX (United States). Dept. of Nuclear Engineering
Description
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
Availability note (English)
Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS DE97008629; NTIS; US GOVT. PRINTING OFFICE DEP.
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Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- LA-UR--97-2268
Conference
- Title
- Joint international conference on mathematical methods and supercomputing in nuclear applications
- Dates
- 6-10 Oct 1997
- Place
- Saratoga Springs, NY (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29053677
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; DOSIMETRY; FAST NEUTRONS; IRRADIATION; MONTE CARLO METHOD; NEUTRONS; PRESSURE VESSELS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CONTAINERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NEUTRONS; NUCLEONS
Optional Information
- Contract/Grant/Project number
- Contract W-7405-ENG-36
- Funding organization
- USDOE Assistant Secretary for Management and Administration, Washington, DC (United States)
- Secondary number(s)
- CONF-971005--