HTGR (High temperature gas-cooled reactor) ingress analysis using MINET

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Book Synopsis HTGR (High temperature gas-cooled reactor) ingress analysis using MINET by : G. J. Van-Tuyle

Download or read book HTGR (High temperature gas-cooled reactor) ingress analysis using MINET written by G. J. Van-Tuyle and published by . This book was released on 1989 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

HTGR (High Temperature Gas-Cooled Reactor) Ingress Analysis Using MINET.

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Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis HTGR (High Temperature Gas-Cooled Reactor) Ingress Analysis Using MINET. by :

Download or read book HTGR (High Temperature Gas-Cooled Reactor) Ingress Analysis Using MINET. written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Modeling of water/steam ingress into the primary (helium) cooling circuit of a High Temperature Gas-Cooled Reactor (HTGR) is described. This modeling was implemented in the MINET Code, which is a program for analyzing transients in intricate fluid flow and heat transfer networks. Results from the simulation of a water ingress event postulated for the Modular HTGR are discussed. 27 refs., 6 figs., 6 tabs.

MINET (Momentum Integral NETwork) Analysis of MHTGR (Modular High Temperature Gas-Cooled Reactor) Moisture-ingress Transient

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Book Synopsis MINET (Momentum Integral NETwork) Analysis of MHTGR (Modular High Temperature Gas-Cooled Reactor) Moisture-ingress Transient by :

Download or read book MINET (Momentum Integral NETwork) Analysis of MHTGR (Modular High Temperature Gas-Cooled Reactor) Moisture-ingress Transient written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The transient which involved a steam-generator tube leak and the ingress of moisture into the primary coolant system of the standard Modular Modular High Temperature Gas-Cooled Reactor (MHTGR) is analyzed by using the MINET (Momentum Integral NETwork) computer code. The analysis provides detailed information on the effect of power excursion on transient system pressures and temperatures. It is concluded that during the short term transient period the moisture ingress presents no threat to the integrity of the fuel elements and does not lead to pressures which would cause relief valve opening and fission product release.

Energy Research Abstracts

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ISBN 13 :
Total Pages : 840 pages
Book Rating : 4.3/5 (129 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1990 with total page 840 pages. Available in PDF, EPUB and Kindle. Book excerpt:

ERDA Energy Research Abstracts

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ISBN 13 :
Total Pages : 848 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis ERDA Energy Research Abstracts by :

Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1989 with total page 848 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Atomic Energy and Nuclear Power

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ISBN 13 :
Total Pages : 40 pages
Book Rating : 4.3/5 (126 download)

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Book Synopsis Atomic Energy and Nuclear Power by : United States. Superintendent of Documents

Download or read book Atomic Energy and Nuclear Power written by United States. Superintendent of Documents and published by . This book was released on 1990 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Air Ingress Analyses on a High Temperature Gas-Cooled Reactor

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Total Pages : pages
Book Rating : 4.:/5 (871 download)

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Book Synopsis Air Ingress Analyses on a High Temperature Gas-Cooled Reactor by :

Download or read book Air Ingress Analyses on a High Temperature Gas-Cooled Reactor written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A primary-pipe break accident is one of the design-basis accidents of a high-temperature gas-cooled reactor (HTGR). When this accident occurs, air is anticipated to enter the reactor core from the break and oxidize the in-core graphite structure in the modular pebble bed reactor (MPBR). This paper presents the results of the graphite oxidation model developed as part of the Idaho National Engineering and Environmental Laboratory's Direct Research and Development effort. Although gas reactors have been tried in the past with limited success, the innovations of modularity and integrated state-ofart control systems coupled with improved fuel design and a pebble bed core make this design potentially very attractive from an economic and technical perspective. A schematic diagram on a reference design of the MPBR has been established on a major component level (INEEL & MIT, 1999). Steady-state and transient thermal hydraulics models will be produced with key parameters established for these conditions at all major components. Development of an integrated plant model to allow for transient analysis on a more sophisticated level is now being developed. In this paper, preliminary results of the hypothetical air ingress are presented. A graphite oxidation model was developed to determine temperature and the control mechanism in the spherical graphite geometry.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

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ISBN 13 : 9789201253101
Total Pages : 639 pages
Book Rating : 4.2/5 (531 download)

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Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency

Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Development of Melcor Input Techniques for High Temperature Gas-cooled Reactor Analysis

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Book Synopsis Development of Melcor Input Techniques for High Temperature Gas-cooled Reactor Analysis by : James Corson

Download or read book Development of Melcor Input Techniques for High Temperature Gas-cooled Reactor Analysis written by James Corson and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: High Temperature Gas-cooled Reactors (HTGRs) can provide clean electricity, as well as process heat that can be used to produce hydrogen for transportation and other sectors. A prototypic HTGR, the Next Generation Nuclear Plant (NGNP), will be built at Idaho National Laboratory. The need for HTGR analysis tools and methods has led to the addition of gas-cooled reactor (GCR) capabilities to the light water reactor code MELCOR. MELCOR will be used by the Nuclear Regulatory Commission licensing of the NGNP and other HTGRs. In the present study, new input techniques have been developed for MELCOR HTGR analysis. These new techniques include methods for modeling radiation heat transfer between solid surfaces in an HTGR, calculating fuel and cladding geometric parameters for pebble bed and prismatic block-type HTGRs, and selecting appropriate input parameters for the reflector component in MELCOR. The above methods have been applied to input decks for a water-cooled reactor cavity cooling system (RCCS); the 400 MW Pebble Bed Modular Reactor (PBMR), the input for which is based on a code-to-code benchmark activity; and the High Temperature Test Facility (HTTF), which is currently in the design phase at Oregon State University. RCCS results show that MELCOR accurately predicts radiation heat transfer rates from the vessel but may overpredict convective heat transfer rates and RCCS coolant flow rates. PBMR results show that thermal striping from hot jets in the lower plenum during steady-state operations, and in the upper plenum during a pressurized loss of forced cooling accident, may be a major design concern. Hot jets could potentially melt control rod drive mechanisms or cause thermal stresses in plenum structures. For the HTTF, results will provide data to validate MELCOR for HTGR analyses. Validation will be accomplished by comparing results from the MELCOR representation of the HTTF to experimental results from the facility. The validation process can be automated using a modular code written in Python, which is described here.

Energy Research Abstracts

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ISBN 13 :
Total Pages : 532 pages
Book Rating : 4.:/5 (3 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on with total page 532 pages. Available in PDF, EPUB and Kindle. Book excerpt:

INIS Atomindeks

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ISBN 13 :
Total Pages : 584 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis INIS Atomindeks by :

Download or read book INIS Atomindeks written by and published by . This book was released on 1988 with total page 584 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The High Temperature Gas-cooled Reactor

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ISBN 13 :
Total Pages : 88 pages
Book Rating : 4.3/5 (9 download)

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Book Synopsis The High Temperature Gas-cooled Reactor by : Kenneth A. Solomon

Download or read book The High Temperature Gas-cooled Reactor written by Kenneth A. Solomon and published by . This book was released on 1980 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Evaluation of High Temperature Gas Cooled Reactor Performace

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ISBN 13 : 9789201162038
Total Pages : 346 pages
Book Rating : 4.1/5 (62 download)

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Book Synopsis Evaluation of High Temperature Gas Cooled Reactor Performace by : International Atomic Energy Agency

Download or read book Evaluation of High Temperature Gas Cooled Reactor Performace written by International Atomic Energy Agency and published by . This book was released on 2003-01-01 with total page 346 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-temperature gas cooled reactor (HTGR) designs persent special computatioal challenges related to their core physics and thermal-hydraulic charectersitics. Neutron streaming and double heterogeneities are examples of the core physics challenges, while porous gas flow in a high-temperature ceramic core with the interaction of conduction, convection and rediation regimes characterize thermal-hydraulic challenges. In an effort to address such potential calculation uncertainties, computational results made by various international institutes are reported and code-to-code and code-to-experiment comparisons are made. The experimental data are mainly related to the initial testing of teh Japanese HTTR and the Chinese HTR-10. Both are high-temperature gas cooled test reactors.The work is part of an IAEA Co-ordinated Research Project (CRP) with the participation of ten international institutes.

Government Reports Announcements & Index

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ISBN 13 :
Total Pages : 1052 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis Government Reports Announcements & Index by :

Download or read book Government Reports Announcements & Index written by and published by . This book was released on 1989 with total page 1052 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Government Reports Annual Index

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ISBN 13 :
Total Pages : 1332 pages
Book Rating : 4.:/5 (3 download)

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Book Synopsis Government Reports Annual Index by :

Download or read book Government Reports Annual Index written by and published by . This book was released on 1991 with total page 1332 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis

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Total Pages : pages
Book Rating : 4.:/5 (946 download)

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Book Synopsis Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis by :

Download or read book Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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. Validation data were available from the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE Handbook), prepared by the International Reactor Physics Experiment Evaluation Project, for two different HTGR designs: prismatic and pebble bed. SCALE models have been developed for HTTR, a prismatic fuel design reactor operated in Japan and HTR-10, a pebble bed reactor operated in China. The models were based on benchmark specifications included in the 2009, 2010, and 2011 releases of the IRPhE Handbook. SCALE models for the HTR-PROTEUS pebble bed configuration at the PROTEUS critical facility in Switzerland have also been developed, based on benchmark specifications included in a 2009 IRPhE draft benchmark. The development of the SCALE models has involved a series of investigations to identify particular issues associated with modeling the physics of HTGRs and to understand and quantify the effect of particular modeling assumptions on calculation-to-experiment comparisons.

H.T.G.R.

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ISBN 13 :
Total Pages : 28 pages
Book Rating : 4.:/5 (757 download)

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Book Synopsis H.T.G.R. by : General Dynamics. General Atomic Division

Download or read book H.T.G.R. written by General Dynamics. General Atomic Division and published by . This book was released on 1964 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: