A Steady State Subchannel Heat Transfer Code for Plate Fueled Reactors PDF Download
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Author: Cory Griffard
Publisher: LAP Lambert Academic Publishing
ISBN: 9783659762727
Category :
Languages : en
Pages : 348
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Book Description
This work develops a plate-fueled reactor subchannel steady state heat transfer code (PFSC) using a one-dimensional subchannel model. Verification and Validation is done for the PFSC by deriving several key equations, which are used in the subchannel heat transfer analysis, from the Reynolds Transport Theorem. This activity allows the subchannel model to be extended to include uncertainties and biases associated with the modeling simplifications. The initial basis for the development of the subchannel code is the High Flux Isotope Reactor (HFIR), which is a leading example of a high performance plate-fueled research reactor. The PFSC includes new features from the existing HFIR Steady State Heat Transfer Code (SSHTC). A code to code comparison is done between the new flexible subchannel code and the HFIR SSHTC, as well as a comparison to an analytical solution for a simplified case with uniform heat flux and constant fluid properties. Biases associated with the one-dimensional assessment of the subchannel model are also reviewed. These activities provide quality assurance for the PFSC.
Author: Cory Griffard
Publisher: LAP Lambert Academic Publishing
ISBN: 9783659762727
Category :
Languages : en
Pages : 348
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Book Description
This work develops a plate-fueled reactor subchannel steady state heat transfer code (PFSC) using a one-dimensional subchannel model. Verification and Validation is done for the PFSC by deriving several key equations, which are used in the subchannel heat transfer analysis, from the Reynolds Transport Theorem. This activity allows the subchannel model to be extended to include uncertainties and biases associated with the modeling simplifications. The initial basis for the development of the subchannel code is the High Flux Isotope Reactor (HFIR), which is a leading example of a high performance plate-fueled research reactor. The PFSC includes new features from the existing HFIR Steady State Heat Transfer Code (SSHTC). A code to code comparison is done between the new flexible subchannel code and the HFIR SSHTC, as well as a comparison to an analytical solution for a simplified case with uniform heat flux and constant fluid properties. Biases associated with the one-dimensional assessment of the subchannel model are also reviewed. These activities provide quality assurance for the PFSC.
Author: Cory Landon Griffard
Publisher:
ISBN:
Category : Heat flux
Languages : en
Pages :
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Book Description
Author: Chengmin Liu
Publisher: Springer Nature
ISBN: 9819910234
Category : Science
Languages : en
Pages : 1179
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Book Description
This is the first in a series of three volumes of proceedings of the 23rd Pacific Basin Nuclear Conference (PBNC 2022) which was held by Chinese Nuclear Society. As one in the most important and influential conference series of nuclear science and technology, the 23rd PBNC was held in Beijing and Chengdu, China in 2022 with the theme “Nuclear Innovation for Zero-carbon Future”. For taking solid steps toward the goals of achieving peak carbon emissions and carbon neutrality, future-oriented nuclear energy should be developed in an innovative way for meeting global energy demands and coordinating the deployment mechanism. It brought together outstanding nuclear scientists and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The proceedings highlight the latest scientific, technological and industrial advances in Nuclear Safety and Security, Operations and Maintenance, New Builds, Waste Management, Spent Fuel, Decommissioning, Supply Capability and Quality Management, Fuel Cycles, Digital Reactor and New Technology, Innovative Reactors and New Applications, Irradiation Effects, Public Acceptance and Education, Economics, Medical and Biological Applications, and also the student program that intends to raise students’ awareness in fully engaging in this career and keep them updated on the current situation and future trends. These proceedings are not only a good summary of the new developments in the field, but also a useful guideline for the researchers, engineers and graduate students. This is an open access book.
Author: Jun Wang
Publisher: Woodhead Publishing
ISBN: 0128181915
Category : Technology & Engineering
Languages : en
Pages : 612
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Book Description
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
The STAT code was written to automate many of the steady-state thermal hydraulic safety calculations for the MIT research reactor, both for conversion of the reactor from high enrichment uranium fuel to low enrichment uranium fuel and for future fuel re-loads after the conversion. A Monte-Carlo statistical propagation approach is used to treat uncertainties in important parameters in the analysis. These safety calculations are ultimately intended to protect against high fuel plate temperatures due to critical heat flux or departure from nucleate boiling or onset of flow instability; but additional margin is obtained by basing the limiting safety settings on avoiding onset of nucleate boiling. STAT7 can simultaneously analyze all of the axial nodes of all of the fuel plates and all of the coolant channels for one stripe of a fuel element. The stripes run the length of the fuel, from the bottom to the top. Power splits are calculated for each axial node of each plate to determine how much of the power goes out each face of the plate. By running STAT7 multiple times, full core analysis has been performed by analyzing the margin to ONB for each axial node of each stripe of each plate of each element in the core.
Author:
Publisher:
ISBN:
Category : Computer software
Languages : en
Pages : 88
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ISBN:
Category : Aeronautics
Languages : en
Pages : 964
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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 934
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Author: L S Tong
Publisher: CRC Press
ISBN: 9781560324850
Category : Science
Languages : en
Pages : 582
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Book Description
Completely updated, this graduate text describes the current state of boiling heat transfer and two-phase flow, in terms through which students can attain a consistent understanding. Prediction of real or potential boiling heat transfer behaviour, both in steady and transient states, is covered to aid engineering design of reliable and effective systems.
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 420
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Book Description
