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2 edition of Evaluation of High Temperature Gas Cooled Reactor Performance found in the catalog.

Evaluation of High Temperature Gas Cooled Reactor Performance

Evaluation of High Temperature Gas Cooled Reactor Performance

Benchmark Analysis Related to Initial Testing of the Httr and Htr-10 (IAEA Tecdoc Series)

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  • 16 Currently reading

Published by International Atomic Energy Agency .
Written in English


The Physical Object
FormatHardcover
ID Numbers
Open LibraryOL12858117M
ISBN 109201162030
ISBN 109789201162038
OCLC/WorldCa68944964

Safety Features of High Temperature Gas Cooled Reactor Chao Fang, 1, 2, 3 Robert Morris, 4 and Fu Li 1, 2, 3 1 Institute of Nuclear and New Energy Cited by: 4. A cross sectional view of the Gas-Cooled Reactor concept is shown in Figure 3 and a more detailed view is in Figwe 4. The fuel is % enriched UN that is clad with rhenium-lined Nb-1Zr. The pin assembly consists of the fuel pin placed in a core matrix (Hastellay X) to form an annular flow passage (including a Re riin-wrap spacer). This approach is similar to the 30 File Size: 4MB. High Temperature Reactors Chapter 4: Technology Assessments Introduction High temperature reactor (HTR) systems (i.e., reactors with core outlet temperatures between °C and °C) offer higher thermodynamic efficiency of converting .


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Evaluation of High Temperature Gas Cooled Reactor Performance Download PDF EPUB FB2

Evaluation Of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related To The PBMR, Pbmm, GT-MHR, HTR And The Astra Critical Facility: IAEA Tecdoc Series No.

[International Atomic Energy Agency] on *FREE* shipping on qualifying offers. Evaluation Of High Temperature Gas Cooled Reactor Performance: Benchmark. Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to the PBMR, PBMM, GT-MHR, HTR and the ASTRA Critical Facility IAEA TECDOC No.

English IAEA-TECDOC Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to Initial Testing of the HTTR and HTR (IAEA TECDOC Series) on *FREE* shipping on qualifying offers.

Very high temperature gas-cooled reactor. A very high temperature gas-cooled reactor (VHTR) is an inherently safe reactor that can produce heat of °C–°C. By virtue of its high temperature heat, a VHTR can be used in high-temperature process heat applications, including hydrogen production and high-efficiency electricity generation.

EVALUATION OF HIGH-TEMPERATURE GAS-COOLED REACTORS. Full Record; Other Related Research; Publication Date: Wed Jan 01 EST Research Org. The Co-ordinated Research Project (CRP) on Evaluation of High Temperature Gas Cooled Reactor (HTGR) Performance was initiated by the IAEA in on the recommendation of the Technical Working Group on Gas Cooled Reactors.

This CRP was established to foster the sharing of research and associated technical information betweenFile Size: 3MB. HIGH TEMPERATURE GAS COOLED REACTOR FUELS AND MATERIALS IAEA, VIENNA, IAEA-TECDOCCD the basis for further development of HTGR fuels and reactor systems.

In many ways this book is a unique source of past experience, and hopefully, it will serve as an important part of Past irradiation performance State of the art in TRISO File Size: 3MB. The very-high-temperature reactor (VHTR), or high-temperature gas-cooled reactor (HTGR), is a Generation IV reactor concept that uses a graphite-moderated nuclear reactor with a once-through uranium fuel cycle.

The VHTR is a type of high-temperature reactor (HTR) that can conceptually have an outlet temperature of °C. The reactor core can be either a. Draft Preapplication Safety Evaluation Report for the Modular High-Temperature Gas-Cooled Reactor (NUREG) was written in early During the late s, the modular HTGR was considered by DOE as one of two possible reactor technologies for materials production (Goodjohn ).

Preliminary. @article{osti_, title = {Modeling and performance of the MHTGR (Modular High-Temperature Gas-Cooled Reactor) reactor cavity cooling system}, author = {Conklin, J C}, abstractNote = {The Reactor Cavity Cooling System (RCCS) of the Modular High- Temperature Gas-Cooled Reactor (MHTGR) proposed by the U.S.

Department of Energy is designed to. The status of high-temperature gas-cooled reactor development and design In the United States and other countries important benefits are foreseen from smaller, modular systems by L.D. Mears and A.J. Goodjohn. Gas-cooled reactors have had a long and varied his-tory dating back to the very early days of nuclear energy development.

A gas-cooled reactor (GCR) is a nuclear reactor that uses graphite as a neutron moderator and carbon dioxide as gh there are many other types of reactor cooled by gas, the terms GCR and to a lesser extent gas cooled reactor are particularly used to refer to this type of reactor.

The GCR was able to use natural uranium as fuel, enabling the countries that. The High Temperature Gas-cooled Reactors (HTGRs), with its inherent safety and high temperature heat supply of about °C at the exterior of the reactor, can achieve effective utilization of nuclear energy in various fields by stages.

For example, HTGRs make it possible to produce hydrogen with its high temperature heat by: Benchmarking of the MIT High Temperature Gas-Cooled Reactor TRISO-Coated Particle Fuel Performance Model by Michael A.

Stawicki Submitted to the Department of Nuclear Science and Engineering on May 5, in partial fulfillment of the requirements for the degrees of Master of Science in Nuclear. By: Diarmuid Foley.

A small modular nuclear reactor to replace coal plants could be on the market within 5 years. Inthe Generation IV international forum confirmed the Very High Temperature Reactor (VHTR) as one of 6 promising reactor technologies that should be pursued in order to develop advanced reactors suitable for deployment in the ’s.

Heat Exchanger Analysis – Heat Exchanger Calculation. Heat exchangers are commonly used in industry, and proper design of a heat exchanger depends on many variables. In the analysis of heat exchangers, it is often convenient to work with an overall heat transfer coefficient, known as a U-factor is defined by an expression analogous to Newton’s law of cooling.

HIGH TEMPERATURE GAS COOLED REACTORS R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada Keywords: High Temperature Gas Cooled Reactors, Pebble Bed Reactors, Reactor Core, Fuel Elements, Control Rods Contents 1.

Introduction Thermodynamic Cycle High Temperature Requirements Historical. T. Ogawa and K. Fukuda, “Performance of the model fuel pin of the very high-temperature gas-cooled reactor at temperatures above °C,” Nucl.

Eng. Des.,92, 15–26 (). Google Scholar Cited by: 4. / (online),/ (print) - Nuclear energy production is a recent technology. The first nuclear reactor demonstrating the feasibility of a sustained and controlled chain reaction was built in Chicago in Ina nuclear reactor produced electricity for the first time.

For the past 60 years, since then a significant technological progress has been. Evaluation of Hydrogen Production System with High Temperature Gas-cooled Reactor Masuro Ogawa* and Shusaku Shiozawa Department of Advanced Nuclear Heat Technology, Japan Atomic Energy Research Institute, Oarai, Ibaraki,Japan The present paper describes hydrogen demand, energy flux of various energies, thermal.

ASSESSMENT OF HIGH TEMPERATURE GAS-COOLED REACTOR (HTGR) CAPITAL AND OPERATING COSTS Identifier: Revision: Effective Date: TEV 1 01/09/ Page: 4 of 45 Table ES Cost Summary for NGNP & NOAK HTGR with a Rankine power cycle, °C ROT ( basis).

Reactor Phase NGNP NOAK Reactor Size MWt MWt MWt MWt. With reference to high temperature electrolysis, Shin et al. [26] proposed a study where a very high temperature gas-cooled reactor (VHTR) is coupled. The performance of very high temperature reactor plants with direct and indirect closed Brayton cycles (CBCs) is compared and the effects of the molecular weight of the CBC working fluid on the number of stages and sizes of the axial flow, single Cited by: 3.

T1 - Process evaluation of use of high temperature gas-cooled reactors to an ironmaking system based on active carbon recycling energy system. AU - Hayashi, Kentaro. AU - Kasahara, Seiji. AU - Kuribara, Kouhei.

AU - Nakagaki, Takao. AU - Yan, Xing L. AU - Inagaki, Yoshiyuki. AU - Ogawa, Masuro. PY - Y1 - Cited by: 1. The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT Initial Evaluation of Fuel-Reactor Concepts for Advanced LEU Fuel.

Development of Local Heat Transfer Models for the Safety Assessment of High Temperature Gas-Cooled Reactor Cores—Part II: Prismatic Modular Reactors J. Eng. Gas Turbines Power (January, ) Advanced High Temperature Gas-Cooled Reactor SystemsCited by: 8.

The special feature of high-temperature gas-cooled reactors (HTGRs) is stressed operating conditions for equipment due to high temperature of the primary circuit helium, up to. high temperature gas cooled reactor (HTGR) prototype and demonstration plants in Britain, Germany, and the U.S.

The focus of these plants was on evolutionary increases in coolant temperature and plant efficiency. An overview of the development of HTGRs is provided in Appendix B, “Brief Survey of Gas-Cooled Reactor Designs.”.

Fluoride-salt-cooled High-temperature Reactor (FHR) The Fluoride-salt-cooled High temperature Reactor (FHR) is a new reactor concept, which combines low-pressure liquid salt coolant and high-temperature TRISO particle fuel. The refractory TRISO particle coating system as well as the dispersion in graphite matrix enhances safeguards and security.

A high-temperature, gas-cooled nuclear reactor consists of a composite cylindrical wall for which a thorium fuel seous helium flows through an annular coolant channel.

Consider conditions for which the helium temperature is Te K and the convection coefficient at the outer surface of the graphite is h WIm.K. r, 8 mm Coolant. High Temperature Engineering Test Reactor (HTTR) of high temperature gas-cooled reactor at Japan Atomic Energy Agency (JAEA) achieved the reactor outlet coolant temperature of °C for the first time in the world at Apr.

19,   This report documents verification and validation studies carried out to assess the performance of the SCALE code system methods and nuclear data for modeling and analysis of High Temperature Gas-Cooled Reactor (HTGR) configurations. (IRPhE Handbook), prepared by the International Reactor Physics Experiment Evaluation Project, for two.

Evaluation of High Temperature Gas Cooled Reactor Performance: Benchmark Analysis Related to the PBMR, PBMM, GT-MHR, HTR and the ASTRA Critical Facility This publication presents the findings of an IAEA coordinated research project (CRP) focusing on validation of the safety and operational aspects of high temperature gas cooled reactors.

Other articles where High-temperature gas-cooled reactor is discussed: nuclear reactor: High-temperature gas-cooled reactors: The high-temperature gas-cooled reactor (HTGR), as mentioned above in Fuel types, is fueled by a mixture of graphite and fuel-bearing microspheres. There are two competitive designs of this reactor type: (1) a German “pebble bed” system that.

for high temperature gas reactor applications. In particular this report addresses the comments provided by INL and documented inTEV Rev.

0, (INL, ). In addition, this report includes updated information on high temperature gas cooled reactors (HTGRs) at the time of writing, as well as additionalFile Size: 1MB. Reactor Demonstration Program and the High Temperature Reactor Development Associates Program to demonstrate the feasibility of a high performance, helium cooled, nuclear power plant.

The reactor achieved initial criticality on March 3,and the plant went into commercial operation in June It operated successfully with a gross capacity. Modular High Temperature Pebble Bed Reactor • Modules added to meet demand. • No Reprocessing •H igh Burnup >90, Mwd/MT •D irect Disposal of HLW • Process Heat Applications - Hydrogen, water • MWe • Helium Cooled • 8 % Enriched Fuel • Built in 2 Years • Factory Built •S ite Assembled • On--line Refueling.

This evaluation and development effort has been coordinated by Gas-Cooled Reactor Associates (GCRA) and supported by all the Program participants. In support of this ongoing effort, GCRA has developed a Lead Project Strategy Plan (Ref. 5) as a framework for negotiations between the prospective Lead Project participants toward the realization of.

as possible solutions. One of these reactors is the High Temperature Reactor (HTR), which consists of a randomly packed bed of fuel pebbles that are cooled by helium. The HTR has proven in the past, with several demonstration plants, that it is an inherently safe reactor, capable of removing the decay heat by passive means in case of loss of.

Design Study on Evaluation for Power Conversion System Concepts in High Temperature Gas Cooled Reactor with Gas Turbine. Isao MINATSUKI 1), Yorikata MIZOKAMI 2) 1) Mitsubishi Heavy Industries, LTD 2) Mitsubishi Heavy Industries, LTD Released /03/07 received /09/21 accepted /03/02 Cited by: 1.

Development of the a high temperature gas cooled reactor (HTGR), a concept with more than three decades of history behind it, in has had several new breakout milestones in China and the U.S.

In March China installed the first of two reactor pressure vessels for a demonstration high temperature, gas cooled (HTGR) (Pebble.(): Study on Tritium Production Using a High-Temperature Gas-Cooled Reactor for Fusion Reactors: Evaluation of Tritium Outflow by Non-Equilibrium Diffusion Simulations, Fusion Science and Technology, DOI: /  A high-temperature nuclear reactor may be cooled by the equivalent volume of helium, air, nitrogen or even carbon dioxide being pumped through the reactor at the same pressure.

The equivalent volume of air will have times the density as helium with up to percent greater thermal capacity with which to cool the reactor.