Comparison of three-dimensional neutron flux calculations for Maine Yankee

Technical Report · Tue Oct 01 00:00:00 EDT 1996

DOI:https://doi.org/10.2172/383640· OSTI ID:383640

Urban, W T; Crotzer, L A; Waters, L S; Parsons, D K; Alcouffe, R E ^[1]; Spinney, K B; Cacciapouti, R J ^[2]

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1. Los Alamos National Lab., NM (United States)
2. Yankee Atomic Electric Co., Bolton, MA (United States)

Calculations have been performed on the Maine Yankee Power Plant to obtain three-dimensional neutron fluxes using the spatial synthesis with the two-dimensional discrete ordinates code DORT, the three-dimensional discrete ordinates code THREEDANT and the three-dimensional Monte Carlo code MCNP. Neutron fluxes are compared for energies above 0.1 MeV and 1.0 MeV as well as dpa. Results were obtained at the Yankee dosimetry locations and special test regions within the pressure vessel, in the reactor cavity, and in a shield tank detector well.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 383640
• Report Number(s): LA-UR-96-2925; CONF-9609243-4; ON: DE96014813; TRN: 96:029077
• Resource Relation: Conference: 9. international symposium on reactor dosimetry, Prague (Czech Republic), 2-6 Sep 1996; Other Information: PBD: [1996]
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
MAINE YANKEE REACTOR
NEUTRON FLUX
THREE-DIMENSIONAL CALCULATIONS
COMPARATIVE EVALUATIONS
DISCRETE ORDINATE METHOD
NEUTRON TRANSPORT
THEORETICAL DATA
MONTE CARLO METHOD