scholarly journals Studies Related to the Oregon State University High Temperature Test Facility: Scaling, the Validation Matrix, and Similarities to the Modular High Temperature Gas-Cooled Reactor

2010 ◽  
Author(s):  
Richard R. Schultz ◽  
Paul D. Bayless ◽  
Richard W. Johnson ◽  
William T. Taitano ◽  
James R. Wolf ◽  
...  
Keyword(s):  
High Temperature ◽  
Test Facility ◽  
State University ◽  
Oregon State University ◽  
Temperature Test ◽  
High Temperature Gas

scholarly journals Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor

2012 ◽  
Author(s):  
Richard R. Schult ◽  
Paul D. Bayless ◽  
Richard W. Johnson ◽  
James R. Wolf ◽  
Brian Woods
Keyword(s):  
High Temperature ◽  
Test Facility ◽  
Temperature Test ◽  
High Temperature Gas

HTGR Component Test Facility (CTF) Feasibility Study for NGNP

2008 ◽  
Author(s):  
Jan P. van Ravenswaay ◽  
Jacques Holtzhausen ◽  
Jaco van der Merwe ◽  
Kobus Olivier ◽  
Riaan du Bruyn ◽  
...  
Keyword(s):  
Heat Transfer ◽  
High Temperature ◽  
Oil Recovery ◽  
Recovery Process ◽  
Initial Energy ◽  
Test Facility ◽  
Design Data ◽  
Component Test ◽  
Maintenance And Inspection ◽  
High Temperature Gas

The Next Generation Nuclear Plant (NGNP) Project is a US-based initiative led by Idaho National Laboratories to demonstrate the viability of using High Temperature Gas-Cooled Reactor (HTGR) technology for the production of high temperature steam and/or heat for applications such as heavy oil recovery, process steam/cogeneration and hydrogen production. A key part of the NGNP Project is the development of a Component Test Facility (CTF) that will support the development of high temperature gas thermal-hydraulic technologies as applied in heat transport and heat transfer applications in HTGRs. These applications include, but are not limited to, primary and secondary coolants, direct cycle power conversion, co-generation, intermediate, secondary and tertiary heat transfer, demonstration of processes requiring high temperatures as well as testing of NGNP specific control, maintenance and inspection philosophies and techniques. The feasibility of the envisioned CTF as a development and testing platform for components and systems in support of the NGNP was evaluated. For components and systems to be integrated into the NGNP full scale or at least representative size tests need to be conducted at NGNP representative conditions, with regards to pressure, flow rate and temperature. Typical components to be tested in the CTF include heat exchangers, steam generators, circulators, valves and gas piping. The Design Data Needs (DDNs), Technology Readiness Levels (TRLs) as well as Design Readiness Levels (DRLs) prepared in the pre-conceptual design of the NGNP Project and the NGNP lifecycle requirements were used as inputs to establish the CTF Functional and Operating Requirements (F&ORs). The existing South African PBMR test facilities were evaluated to determine their current applicability or possible modifications to meet the F&ORs of the CTF. Three concepts were proposed and initial energy balances and layouts were developed. This paper will present the results of this CTF study and the ongoing efforts to establish the CTF.

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

2018 ◽  
Vol 4 (3) ◽  
Author(s):  
Yongyong Wu ◽  
Cheng Ren ◽  
Rui Li ◽  
Xingtuan Yang ◽  
Jiyuan Tu ◽  
...  
Keyword(s):  
High Temperature ◽  
Thermal Diffusivity ◽  
Inverse Method ◽  
Experimental Result ◽  
Test Facility ◽  
Inherent Safety ◽  
Pebble Bed ◽  
Effective Thermal Diffusivity ◽  
Under Construction ◽  
High Temperature Gas

The effective thermal diffusivity and conductivity of pebble bed in the high temperature gas-cooled reactor (HTGR) are two vital parameters to determine the operating temperature and power in varisized reactors with the restriction of inherent safety. A high-temperature heat transfer test facility and its inverse method for processing experimental data are presented in this work. The effective thermal diffusivity as well as conductivity of pebble bed will be measured at temperature up to 1600 °C in the under-construction facility with the full-scale in radius. The inverse method gives a global optimal relationship between thermal diffusivity and temperature through those thermocouple values in the pebble bed facility, and the conductivity is obtained by conversion from diffusivity. Furthermore, the robustness and uncertainty analyses are also set forth here to illustrate the validity of the algorithm and the corresponding experiment. A brief experimental result of preliminary low-temperature test is also presented in this work.

scholarly journals Evaluation of Fuel Temperature on High Temperature Test Operation at High Temperature Gas-Cooled Reactor 'HTTR'

2006 ◽  
Vol 5 (1) ◽  
pp. 57-67 ◽  
Author(s):  
Daisuke TOCHIO ◽  
Junya SUMITA ◽  
Eiji TAKADA ◽  
Nozomu FUJIMOTO ◽  
Shigeaki NAKAGAWA
Keyword(s):  
High Temperature ◽  
Fuel Temperature ◽  
Test Operation ◽  
Temperature Test ◽  
High Temperature Gas

scholarly journals Analyses of the OSU-MASLWR Experimental Test Facility

2012 ◽  
Vol 2012 ◽  
pp. 1-19 ◽  
Author(s):  
F. Mascari ◽  
G. Vella ◽  
B. G. Woods ◽  
F. D'Auria
Keyword(s):  
Natural Circulation ◽  
Developed Countries ◽  
System Level ◽  
Test Facility ◽  
State University ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Standard Problem ◽  
Oregon State University

Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community starts the development of new advanced reactor designs. In this framework, Oregon State University (OSU) has constructed, a system level test facility to examine natural circulation phenomena of importance to multi-application small light water reactor (MASLWR) design, a small modular pressurized water reactor (PWR), relying on natural circulation during both steady-state and transient operation. The target of this paper is to give a review of the main characteristics of the experimental facility, to analyse the main phenomena characterizing the tests already performed, the potential transients that could be investigated in the facility, and to describe the current IAEA International Collaborative Standard Problem that is being hosted at OSU and the experimental data will be collected at the OSU-MASLWR test facility. A summary of the best estimate thermal hydraulic system code analyses, already performed, to analyze the codes capability in predicting the phenomena typical of the MASLWR prototype, thermal hydraulically characterized in the OSU-MASLWR facility, is presented as well.

scholarly journals The Component Test Facility: A National User Facility for Testing of High Temperature Gas-Cooled Reactor (HTGR) Components and Systems

2008 ◽  
Author(s):  
Vondell J. Balls ◽  
David S. Duncan ◽  
Stephanie L. Austad
Keyword(s):  
High Temperature ◽  
Large Scale ◽  
High Efficiency ◽  
Scale Effects ◽  
Nuclear Plant ◽  
Department Of Energy ◽  
Test Facility ◽  
Component Test ◽  
User Facility ◽  
High Temperature Gas

The Next Generation Nuclear Plant (NGNP) and other High-Temperature Gas-cooled Reactor (HTGR) Projects require research, development, design, construction, and operation of a nuclear plant intended for both high-efficiency electricity production and high-temperature industrial applications, including hydrogen production. During the life cycle stages of an HTGR, plant systems, structures and components (SSCs) will be developed to support this reactor technology. To mitigate technical, schedule, and project risk associated with development of these SSCs, a large-scale test facility is required to support design verification and qualification prior to operational implementation. As a full-scale helium test facility, the Component Test facility (CTF) will provide prototype testing and qualification of heat transfer system components (e.g., Intermediate Heat Exchanger, valves, hot gas ducts), reactor internals, and hydrogen generation processing. It will perform confirmation tests for large-scale effects, validate component performance requirements, perform transient effects tests, and provide production demonstration of hydrogen and other high-temperature applications. Sponsored wholly or in part by the U.S. Department of Energy, the CTF will support NGNP and will also act as a National User Facility to support worldwide development of High-Temperature Gas-cooled Reactor technologies.

The RELAP5 Simulation of 2″ LOCA of APEX Facility

2010 ◽  
Author(s):  
Heng Xie
Keyword(s):  
Test Facility ◽  
State University ◽  
Pressurized Water Reactor ◽  
Reduced Pressure ◽  
Pressurized Water ◽  
Sequence Of Events ◽  
Comparison Results ◽  
Integral Systems ◽  
Oregon State University ◽  
Good Agreement

The RELAP5/SCDAP Mod3.2(am5) code is employed to simulate the OSU-AP1000-05 test conducted in the Advanced Plant Experimental (APEX) test facility at Oregon State University (OSU). The APEX-1000 test facility is an one-fourth height, one-half time scale, and reduced pressure integral systems facility to simulate the Westinghouse Advanced Passive 1000 MW (AP1000) pressurized water reactor. OSU-AP1000-05 is a two-inch break at the bottom of cold leg #4 with 3 out of 4 ADS-4 valves of OSU-APEX-1000 facility. RELAP5 predictions are compared to the experimental data generated by the test. The comparison shows good agreement between the predicted and measured sequence of events of some key parameters during the transient. From the comparison results, it could be preliminary concluded that the RELAP5/SCDAP Mod3.2(am5) code are suitable to simulate the small LOCA of APEX.

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