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in subjects: "Thermal Hydraulics"  
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Thermal Hydraulics of the Very High Temperature Gas Cooled Reactor

Description: The U.S Department of Energy (DOE) is conducting research on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core will be either a prismatic graphite block type core or a pebble bed core. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, … more
Date: October 1, 2009
Creator: Oh, Chang; Kim, Eung; Schultz, Richard; Patterson, Mike & Petti, Davie
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

NEAMS Experimental Support for Code Validation, INL FY2009

Description: The goal is for all modeling and simulation tools to be demonstrated accurate and reliable through a formal Verification and Validation (V&V) process, especially where such tools are to be used to establish safety margins and support regulatory compliance, or to design a system in a manner that reduces the role of expensive mockups and prototypes. Whereas the Verification part of the process does not rely on experiment, the Validation part, on the contrary, necessitates as many relevant and pre… more
Date: September 1, 2009
Creator: Youinou, G.; Palmiotti, G.; Salvatore, M. & Rabiti, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Method and System for the Production of Hydrogen at Reduced VHTR Outlet Temperatures

Description: The Department of Energy and the Idaho National Laboratory are developing a Next Generation Nuclear Plant (NGNP) to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold 1) efficient low cost energy generation and 2) hydrogen production. Although a next generation plant could be developed as a single-purpose facility dedicated to hydrogen production, early designs are expected to be dual purpose. While hydrogen production and advanced ener… more
Date: October 1, 2009
Creator: Oh, Chang H. & Kim, Eung S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal Analysis of a Uranium Silicide Miniplate Irradiation Experiment

Description: This paper outlines the thermal analysis for the irradiation of high density uranium-silicide (U3Si2 dispersed in an aluminum matrix and clad in aluminum) booster fuel for a Boosted Fast Flux Loop designed to provide fast neutron flux test capability in the ATR. The purpose of this experiment (designated as Gas Test Loop-1 [GTL-1]) is two-fold: (1) to assess the adequacy of the U3Si2/Al dispersion fuel and the aluminum alloy 6061 cladding, and (2) to verify stability of the fuel cladding boehmi… more
Date: September 1, 2009
Creator: Guillen, Donna Post
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development of Mechanistic Modeling Capabilities for Local Neutronically-Coupled Flow-Induced Instabilities in Advanced Water-Cooled Reactors

Description: The major research objectives of this project included the formulation of flow and heat transfer modeling framework for the analysis of flow-induced instabilities in advanced light water nuclear reactors such as boiling water reactors. General multifield model of two-phase flow, including the necessary closure laws. Development of neurton kinetics models compatible with the proposed models of heated channel dynamics. Formulation and encoding of complete coupled neutronics/thermal-hydraulics mod… more
Date: November 30, 2009
Creator: Podowski, Michael
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Feasibility, Design, and Hazard Analysis of a Boiling Water Test Loop Within the Idaho National Laboratory Advanced Test Reactor National Scientific User Facility

Description: The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The ATR and its support facilities are located at the Idaho National Laboratory (INL). A Boiling Water Test Loop (BWTL) is being designed for one of the irradiation test positions within the. The objective of the new loop will be to simulate boiling water reactor (BWR) condit… more
Date: May 1, 2009
Creator: Gerstner, Douglas M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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