Author: U.S. Nuclear Regulatory Commission. Special Inquiry Group
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 214
Book Description
Three Mile Island
Author: U.S. Nuclear Regulatory Commission. Special Inquiry Group
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 214
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 214
Book Description
International Fuel Gas Code Turbo Tabs 2018
Author: International Code Council
Publisher:
ISBN: 9781609837242
Category :
Languages : en
Pages :
Book Description
Customize your 2018 INTERNATIONAL FUEL GAS CODE Soft Cover book with updated, easy-to-use TURBO TABS. These handy tabs will highlight the most frequently referenced sections of the latest version of the IFGC. They have been strategically designed by industry experts so that users can quickly and efficiently access the information they need, when they need it.
Publisher:
ISBN: 9781609837242
Category :
Languages : en
Pages :
Book Description
Customize your 2018 INTERNATIONAL FUEL GAS CODE Soft Cover book with updated, easy-to-use TURBO TABS. These handy tabs will highlight the most frequently referenced sections of the latest version of the IFGC. They have been strategically designed by industry experts so that users can quickly and efficiently access the information they need, when they need it.
The Safety of Nuclear Power Reactors (light Water-cooled) and Related Facilities
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 528
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 528
Book Description
Thermal and Flow Design of Helium-cooled Reactors
Author: Gilbert Melese
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 444
Book Description
This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 444
Book Description
This source book provides both an overview of gas-cooled reactors and a detailed look at the high-temperature gas-cooled reactor (HTGR). Taking a worldwide perspective, this book reviews the early development of the HTGR and explores potential future development and applications.
Nuclear Regulatory Commission Issuances
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 950
Book Description
Safe Handling of Tritium
Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 148
Book Description
This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D.
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 148
Book Description
This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D.
Safety Margins of Operating Rectors
Author: M. Antila
Publisher: International Atomic Energy Agency
ISBN: 9789201181022
Category : Business & Economics
Languages : en
Pages : 145
Book Description
This TECDOC deals with a basic concept of safety margins and their role in assuring safety of nuclear Installations. The document describes capabilities of thermal hydraulic computer codes used to determine safety margins, evaluation of uncertainties, methods for safety margin evaluation and utilization of safety margins in operation and modifications of nuclear power plants.
Publisher: International Atomic Energy Agency
ISBN: 9789201181022
Category : Business & Economics
Languages : en
Pages : 145
Book Description
This TECDOC deals with a basic concept of safety margins and their role in assuring safety of nuclear Installations. The document describes capabilities of thermal hydraulic computer codes used to determine safety margins, evaluation of uncertainties, methods for safety margin evaluation and utilization of safety margins in operation and modifications of nuclear power plants.
Guidelines for Design and Construction of Hospital and Health Care Facilities
Author: AIA Academy of Architecture for Health
Publisher:
ISBN:
Category : Medical
Languages : en
Pages : 210
Book Description
Reflecting the most current thinking about infection control and the environment of care, this new edition also explores functional, space, and equipment requirements for acute care and psychiatric hospitals; nursing, outpatient, and rehabilitation facilities; mobile health care units; and facilities for hospice care, adult day care, and assisted living. [Editor, p. 4 cov.]
Publisher:
ISBN:
Category : Medical
Languages : en
Pages : 210
Book Description
Reflecting the most current thinking about infection control and the environment of care, this new edition also explores functional, space, and equipment requirements for acute care and psychiatric hospitals; nursing, outpatient, and rehabilitation facilities; mobile health care units; and facilities for hospice care, adult day care, and assisted living. [Editor, p. 4 cov.]
Physics of High-Temperature Reactors
Author: Luigi Massimo
Publisher: Elsevier
ISBN: 1483280284
Category : Technology & Engineering
Languages : en
Pages : 249
Book Description
Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
Publisher: Elsevier
ISBN: 1483280284
Category : Technology & Engineering
Languages : en
Pages : 249
Book Description
Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal
Author: International Atomic Energy Agency
Publisher: IAEA Tecdoc Series No. 1790
ISBN: 9789201040169
Category : Technology & Engineering
Languages : en
Pages : 0
Book Description
Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal.
Publisher: IAEA Tecdoc Series No. 1790
ISBN: 9789201040169
Category : Technology & Engineering
Languages : en
Pages : 0
Book Description
Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal.