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High Temperature Gas Reactors: Assessment of Applicable Codes and Standards

Description: Current interest expressed by industry in HTGR plants, particularly modular plants with power up to about 600 MW(e) per unit, has prompted NRC to task PNNL with assessing the currently available literature related to codes and standards applicable to HTGR plants, the operating history of past and present HTGR plants, and with evaluating the proposed designs of RPV and associated piping for future plants. Considering these topics in the order they are arranged in the text, first the operational … more
Date: October 31, 2011
Creator: McDowell, Bruce K.; Nickolaus, James R.; Mitchell, Mark R.; Swearingen, Gary L. & Pugh, Ray
Partner: UNT Libraries Government Documents Department
open access

EVALUATION OF ALTERNATIVE FILTER MEDIA FOR THE ROTARY MICROFILTER, PHASE 2

Description: Testing was conducted at the Savannah River National Laboratory (SRNL) to investigate filter membrane performance in an effort to increase rotary microfilter (RMF) throughput. Membranes were tested in the SpinTek Filtration, Inc. Static Test Cell (STC), which permitted quick and easy testing of several different membranes. Testing consisted of 100 hours tests with two different slurry feeds, based on recommendations from the phase 1 testing. One feed contained Monosodium Titanate (MST) solids i… more
Date: July 31, 2012
Creator: Fowley, M.
Partner: UNT Libraries Government Documents Department
open access

Code Qualification of Structural Materials for AFCI Advanced Recycling Reactors.

Description: This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Ca… more
Date: May 31, 2012
Creator: Natesan, K.; Li, M.; Majumdar, S.; Nanstad, R. K. & Sham, T.-L.
Partner: UNT Libraries Government Documents Department
open access

Human-system Interfaces to Automatic Systems: Review Guidance and Technical Basis

Description: Automation has become ubiquitous in modern complex systems and commercial nuclear power plants are no exception. Beyond the control of plant functions and systems, automation is applied to a wide range of additional functions including monitoring and detection, situation assessment, response planning, response implementation, and interface management. Automation has become a 'team player' supporting plant personnel in nearly all aspects of plant operation. In light of the increasing use and imp… more
Date: January 31, 2010
Creator: Ohara, J. M. & Higgins, J. C.
Partner: UNT Libraries Government Documents Department
open access

Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration

Description: Development and deployment of small-scale nuclear power reactors and their maintenance, monitoring, and control are part of the mission under the Small Modular Reactor (SMR) program. The objectives of this NERI-consortium research project are to investigate, develop, and validate advanced methods for sensing, controlling, monitoring, diagnosis, and prognosis of these reactors, and to demonstrate the methods with application to one of the proposed integral pressurized water reactors (IPWR). For … more
Date: May 31, 2011
Creator: Hines, J. Wesley; Upadhyaya, Belle R.; Doster, J. Michael; Edwards, Robert M.; Lewis, Kenneth D.; Turinsky, Paul et al.
Partner: UNT Libraries Government Documents Department
open access

Advances in coupled safety modeling using systems analysis and high-fidelity methods.

Description: The potential for a sodium-cooled fast reactor to survive severe accident initiators with no damage has been demonstrated through whole-plant testing in EBR-II and FFTF. Analysis of the observed natural protective mechanisms suggests that they would be characteristic of a broad range of sodium-cooled fast reactors utilizing metal fuel. However, in order to demonstrate the degree to which new, advanced sodium-cooled fast reactor designs will possess these desired safety features, accurate, high-… more
Date: May 31, 2010
Creator: Fanning, T. H.; Thomas, J. W. & Division, Nuclear Engineering
Partner: UNT Libraries Government Documents Department
open access

A Comparative Study of Welded ODS Cladding materials for AFCI/GNEP Applications

Description: This research project involved working on the pressure resistance welding of oxide dispersion strengthened (ODS) alloys which will have a large role to play in advanced nuclear reactors. The project also demonstrated the research collaboration between four universities and one nation laboratory (Idaho National Laboratory) with participation from an industry for developing for ODS alloys. These alloys contain a high number density of very fine oxide particles that can impart high temperature str… more
Date: March 31, 2011
Creator: Charit, Indrajit; Frary, Megan; Butt, Darryl; Murty, K.L.; Zirker, Larry; Cole, James et al.
Partner: UNT Libraries Government Documents Department
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