FRAPCON-3: A Computer Code For The Calculation Of Steady-State, Thermal-Mechanical Behavior Of Oxide Fuel Rods For High Burnup... NUREG/CR-6534, Vol. 2 PNNL-11513... U.S. Nuclear Reg. Commission

FRAPCON-3: A Computer Code For The Calculation Of Steady-State, Thermal-Mechanical Behavior Of Oxide Fuel Rods For High Burnup... NUREG/CR-6534, Vol. 2 PNNL-11513... U.S. Nuclear Reg. Commission PDF Author:
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Languages : en
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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

Fundamentals of Nuclear Engineering

Fundamentals of Nuclear Engineering PDF Author: Brent J. Lewis
Publisher: John Wiley & Sons
ISBN: 1119271495
Category : Science
Languages : en
Pages : 980

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Book Description
Fundamental of Nuclear Engineering is derived from over 25 years of teaching undergraduate and graduate courses on nuclear engineering. The material has been extensively class tested and provides the most comprehensive textbook and reference on the fundamentals of nuclear engineering. It includes a broad range of important areas in the nuclear engineering field; nuclear and atomic theory; nuclear reactor physics, design, control/dynamics, safety and thermal-hydraulics; nuclear fuel engineering; and health physics/radiation protection. It also includes the latest information that is missing in traditional texts, such as space radiation. The aim of the book is to provide a source for upper level undergraduate and graduate students studying nuclear engineering.

Proceedings of the 2023 Water Reactor Fuel Performance Meeting

Proceedings of the 2023 Water Reactor Fuel Performance Meeting PDF Author: Jianqiao Liu
Publisher: Springer Nature
ISBN: 9819971578
Category : Science
Languages : en
Pages : 384

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Book Description
The Water Reactor Fuel Performance Meeting (WRFPM) held in Asia has merged with TopFuel in Europe and LWR Fuel Performance in the United States to form the globally most influential conference in the field of nuclear fuel research. WRFPM2023 is organized by Chinese Nuclear Society (CNS) in cooperation with the Atomic Energy Society of Japan (AESJ), Korean Nuclear Society (KNS), European Nuclear Society (ENS), American Nuclear Society (ANS), the Interna-tional Atomic Energy Agency (IAEA) with the support from China Nuclear Energy In¬dustry Corporation (CNEIC) and TVEL. Conference Topics: 1. Advances in water reactor fuel technology and testing 2. Operation and experience 3. Transient and off-normal fuel behaviour and safety related issues 4. Fuel cycle, used fuel storage and transportation 5. Innovative fuel and related issues 6. Fuel modelling, analysis and methodology

FRAPCON-3: A COMPUTER CODE FOR THE CALCULATION OF STEADY-STATE, THERMAL-MECHANICAL BEHAVIOR OF OXIDE FUEL RODS FOR HIGH BURNUP... NUREG

FRAPCON-3: A COMPUTER CODE FOR THE CALCULATION OF STEADY-STATE, THERMAL-MECHANICAL BEHAVIOR OF OXIDE FUEL RODS FOR HIGH BURNUP... NUREG PDF Author: U.S. Nuclear Regulatory Commission
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Languages : en
Pages :

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Proceedings of the Seminar on Thermal Performance of High Burn-up LWR Fuel

Proceedings of the Seminar on Thermal Performance of High Burn-up LWR Fuel PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 400

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Book Description
LWR = Light water reactor. On title page: OECD proceedings. On cover: Nuclear science

FRAPCON-3

FRAPCON-3 PDF Author: Gary A. Berna
Publisher:
ISBN: 9780160628832
Category : Computer-aided engineering
Languages : en
Pages : 118

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FRAPCON-3.4

FRAPCON-3.4 PDF Author: K. J. Geelhood
Publisher:
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Category : Computer-aided engineering
Languages : en
Pages : 0

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Transactions of the American Nuclear Society

Transactions of the American Nuclear Society PDF Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 922

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FRAPCON-2

FRAPCON-2 PDF Author: Gary A. Berna
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 300

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