FRAPCON-2

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

Get Book Here

Book Description

FRAPCON-2

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

Get Book Here

Book Description


NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 300

Get Book Here

Book Description


FRAPCON-2 Developmental Assessment

FRAPCON-2 Developmental Assessment PDF Author: Gary A. Berna
Publisher:
ISBN:
Category : Heat
Languages : en
Pages : 166

Get Book Here

Book Description


Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 988

Get Book Here

Book Description


Reactor Safety Research Programs

Reactor Safety Research Programs PDF Author: S. K. Edler
Publisher:
ISBN:
Category : Water cooled reactors
Languages : en
Pages : 96

Get Book Here

Book Description


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

Get Book Here

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

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 508

Get Book Here

Book Description


Evaluation of Power Reactor Fuel Rod Analysis Capabilities: Code evaluation

Evaluation of Power Reactor Fuel Rod Analysis Capabilities: Code evaluation PDF Author: Dennis R. Coleman
Publisher:
ISBN:
Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 104

Get Book Here

Book Description


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

Get Book Here

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

Nuclear Safety

Nuclear Safety PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 136

Get Book Here

Book Description