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Topical report : CFD analysis for the applicability of the natural convection shutdown heat removal test facility (NSTF) for the simulation of the VHTR RCCS.

Description: The Very High Temperature gas cooled reactor (VHTR) is one of the GEN IV reactor concepts that have been proposed for thermochemical hydrogen production and other process-heat applications like coal gasification. The United States Department of Energy has selected the VHTR for further research and development, aiming to demonstrate emissions-free electricity and hydrogen production at a future time. One of the major safety advantages of the VHTR is the potential for passive decay heat removal b… more
Date: May 16, 2007
Creator: Tzanos, C. P. (Nuclear Engineering Division)
Partner: UNT Libraries Government Documents Department
open access

NEAMS Update. Quarterly Report for October - December 2011.

Description: The Advanced Modeling and Simulation Office within the DOE Office of Nuclear Energy (NE) has been charged with revolutionizing the design tools used to build nuclear power plants during the next 10 years. To accomplish this, the DOE has brought together the national laboratories, U.S. universities, and the nuclear energy industry to establish the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program. The mission of NEAMS is to modernize computer modeling of nuclear energy systems and … more
Date: February 16, 2012
Creator: Bradley, K. (Nuclear Engineering Division)
Partner: UNT Libraries Government Documents Department
open access

Structured hints : extracting and abstracting domain expertise.

Description: We propose a new framework for providing information to help optimize domain-specific application codes. Its design addresses problems that derive from the widening gap between the domain problem statement by domain experts and the architectural details of new and future high-end computing systems. The design is particularly well suited to program execution models that incorporate dynamic adaptive methodologies for live tuning of program performance and resource utilization. This new framework,… more
Date: March 16, 2009
Creator: Hereld, M.; Stevens, R.; Sterling, T.; Gao, G. R.; Science, Mathematics and Computer; Tech., California Inst. of et al.
Partner: UNT Libraries Government Documents Department
open access

Status report on multigroup cross section generation code development for high-fidelity deterministic neutronics simulation system.

Description: Under the fast reactor simulation program launched in April 2007, development of an advanced multigroup cross section generation code was initiated in July 2007, in conjunction with the development of the high-fidelity deterministic neutron transport code UNIC. The general objectives are to simplify the existing multi-step schemes and to improve the resolved and unresolved resonance treatments. Based on the review results of current methods and the fact that they have been applied successfully … more
Date: May 16, 2008
Creator: Yang, W. S. & Lee, C. H. (Nuclear Engineering Division)
Partner: UNT Libraries Government Documents Department
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