MELCOR Model and Analysis of UW Water-cooled Reactor Cavity Cooling System

MELCOR Model and Analysis of UW Water-cooled Reactor Cavity Cooling System PDF Author: Jae Jong Oh
Publisher:
ISBN:
Category :
Languages : en
Pages : 188

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MELCOR Model and Analysis of UW Water-cooled Reactor Cavity Cooling System

MELCOR Model and Analysis of UW Water-cooled Reactor Cavity Cooling System PDF Author: Jae Jong Oh
Publisher:
ISBN:
Category :
Languages : en
Pages : 188

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Onset of Boiling and Two-phase Flow Behavior Analysis of an UW Water-cooled Reactor Cavity Cooling System with RELAP5

Onset of Boiling and Two-phase Flow Behavior Analysis of an UW Water-cooled Reactor Cavity Cooling System with RELAP5 PDF Author: Sowun Kim
Publisher:
ISBN:
Category :
Languages : en
Pages : 238

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CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications

CFD Model Development and Validation for High Temperature Gas Cooled Reactor Cavity Cooling System (RCCS) Applications PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
The Reactor Cavity Cooling Systems (RCCS) is a passive safety system that will be incorporated in the VTHR design. The system was designed to remove the heat from the reactor cavity and maintain the temperature of structures and concrete walls under desired limits during normal operation (steady-state) and accident scenarios. A small scale (1:23) water-cooled experimental facility was scaled, designed, and constructed in order to study the complex thermohydraulic phenomena taking place in the RCCS during stead-state and transient conditions. The facility represents a portion of the reactor vessel with nine stainless steel coolant risers and utilizes water as coolant. The facility was equipped with instrumentation to measure temperatures and flow rates and a general verification was completed during the shakedown. A model of the experimental facility was prepared using RELAP5-3D and simulations were performed to validate the scaling procedure. The experimental data produced during the stead-state run were compared with the simulation results obtained using RELAP5-3D. The overall behavior of the facility met the expectations. The facility capabilities were confirmed to be very promising in performing additional experimental tests, including flow visualization, and produce data for code validation.

1D and 3D Simulation of a Water-cooled Reactor Cavity Cooling System Experimental Facility

1D and 3D Simulation of a Water-cooled Reactor Cavity Cooling System Experimental Facility PDF Author:
Publisher:
ISBN:
Category : Electronic dissertations
Languages : en
Pages : 323

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Book Description
Natural circulation -- Reactor cavity cooling system -- 1D systems CFD -- 3D CFD -- 1D/3D coupling -- Natuurlike sirkulasie -- Reaktor ruimte verkoeling stelsel -- 1D stelsel berekenings vloei dinamika -- 3D berekenings vloei dinamika -- 1D/3D koppeling.

Nuclear Safety in Light Water Reactors

Nuclear Safety in Light Water Reactors PDF Author: Bal Raj Sehgal
Publisher: Academic Press
ISBN: 0123884462
Category : Technology & Engineering
Languages : en
Pages : 732

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Book Description
La 4e de couverture indique : Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information.

Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes PDF 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

Challenges for Coolants in Fast Neutron Spectrum Systems

Challenges for Coolants in Fast Neutron Spectrum Systems PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201078209
Category :
Languages : en
Pages : 268

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Book Description
This publication evaluates the different coolant options considered for nuclear applications with a fast neutron spectrum (i.e. fusion, fission and accelerators), compiles the latest information in the field and identifies research needs.

Reactor Core Materials

Reactor Core Materials PDF Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 304

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NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 48

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Methods in Protein Structure Analysis

Methods in Protein Structure Analysis PDF Author: M. Zouhair Atassi
Publisher: Springer Science & Business Media
ISBN: 148991031X
Category : Science
Languages : en
Pages : 522

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Book Description
The MPSA international conference is held in a different country every two years. It is devoted to methods of determining protein structure with emphasis on chemistry and sequence analysis. Until the ninth conference, MPSA was an acronym for Methods in Protein Sequence Analysis. To give the conference more flexibility and breadth, the Scientific Advisory Committee of the lOth MPSA decided to change the name to Methods in Protein Structure Analysis; however, the emphasis remains on "methods" and on "chemistry. " In fact, this is the only major conference that is devoted to methods. The MPSA conference is truly international, a fact clearly reflected by the composi tion of its Scientific Advisory Committee. The Scientific Advisory Committee oversees the scientific direction of the MPSA and elects the chairman of the conference. Members of the committee are elected by active members, based on scientific standing and activity. The chairman, subject to approval of the Scientific Advisory Committee, appoints the Organizing Committee. It is this latter committee that puts the conference together. The lectures of the MPSA have traditionally been published in a special proceedings issue. This is different from, and more detailed than, the special MPSA issue of the Journal of Protein Chemistry in which only a brief description of the talks is given in short papers and abstracts. In the I Oth MPSA, about half the talks are by invited speakers and the remainder were selected from submitted short papers and abstracts.