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Artigo
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Comparison of the 3-D Deterministic Neutron Transport Code Attila® To Measure Data, MCNP And MCNPX For The Advanced Test Reactor

Lucas, D. Scott ; Lucas, D. S. United States. Department Of Energy.

M&CInternational Topical,Avignon, FR, 09/15/2005

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Investigating the Use of 3-D Deterministic Transport for Core Safety Analysis

Gougar, H. D. ; Scott, D. United States. Department Of Energy.

physor,chicago, 04/29/2004

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3
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Artigo
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Applications of the 3-D Deterministic Transport Code Attlla for Core Safety Analysis

Lucas, D. S. United States. Office Of The Assistant Secretary For Nuclear Energy.

Conference of the Americas,Miami Beach, FL, 10/06/2004

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4
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Artigo
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Experiences in the Performance Analysis and Optimization of a Deterministic Radiation Transport Code on the Cray SV1

Cebull, Peter United States. Department Of Energy.

Cray User Group Meeting,Knoxville, TN, 05/21/2004

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5
Material Type:
Tese
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COUPLED MULTI-GROUP NEUTRON PHOTON TRANSPORT FOR THE SIMULATION OF HIGH-RESOLUTION GAMMA-RAY SPECTROSCOPY APPLICATIONS

Burns, Kimberly A. United States. Department Of Energy.

Pacific Northwest National Laboratory (U.S.) 2009

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6
Material Type:
Recurso Textual
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Next-Generation Solar Collectors for CSP, Concentrating Solar Power (Fact Sheet)

Solar Energy Technologies Program

National Renewable Energy Laboratory (U.S.) 2012

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