The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box

The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box PDF Author: Randall Owen Gauntt
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 204

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The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box

The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box PDF Author: Randall Owen Gauntt
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 204

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The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box

The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box PDF Author: Randall Owen Gauntt
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 196

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Reactor Safety Research Semiannual Report

Reactor Safety Research Semiannual Report PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 366

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Results of the DF-4 BWR (boiling Water Reactor) Control Blade-channel Box Test

Results of the DF-4 BWR (boiling Water Reactor) Control Blade-channel Box Test PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 15

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Book Description
The DF-4 in-pile fuel damage experiment investigated the behavior of boiling water reactor (BWR) fuel canisters and control blades in the high temperature environment of an unrecovered reactor accident. This experiment, which was carried out in the Annular Core Research Reactor (ACRR) at Sandia National Laboratories, was performed under the USNRC's internationally sponsored severe fuel damage (SFD) program. The DF-4 test is described herein and results from the experiment are presented. Important findings from the DF-4 test include the low temperature melting of the stainless steel control blade caused by reaction with the B4C, and the subsequent low temperature attack of the Zr-4 channel box by the relocating molten blade components. Hydrogen generation was found to continue throughout the experiment, diminishing slightly following the relocation of molten oxidizing zircaloy to the lower extreme of the test bundle. A large blockage which was formed from this material continued to oxidize while steam was being fed into the the test bundle. The results of this test have provided information on the initial stages of core melt progression in BWR geometry involving the heatup and cladding oxidation stages of a severe accident and terminating at the point of melting and relocation of the metallic core components. The information is useful in modeling melt progression in BWR core geometry, and provides engineering insight into the key phenomena controlling these processes. 12 refs., 12 figs.

Nuclear Thermal Hydraulic and Two-Phase Flow

Nuclear Thermal Hydraulic and Two-Phase Flow PDF Author: Jun Wang
Publisher: Frontiers Media SA
ISBN: 2889456129
Category :
Languages : en
Pages : 120

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Book Description
Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.

Fission Product Processes In Reactor Accidents

Fission Product Processes In Reactor Accidents PDF Author: J. T. Rogers
Publisher: CRC Press
ISBN: 1000158624
Category : Science
Languages : en
Pages : 742

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Book Description
The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 438

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Advances in Nuclear Science and Technology

Advances in Nuclear Science and Technology PDF Author: Jeffery Lewins
Publisher: Springer Science & Business Media
ISBN: 0306478110
Category : Science
Languages : en
Pages : 328

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Book Description
Some countries have moved beyond the design and operation of nuclear electricity generating systems to confronting the issue of nuclear waste disposal, whole others are still committed to further nuclear facility construction. Volume 24 chronicles these key developments and examines nuclear reactor accidents at Chernobyl, Bhopal, and TMI. The text also analyzes current international knowledge of neutron interactions; deterministic methods based on mean values for assessing radiation distributions; practical applications of the TIBERE models to explicit computation of leakage terms in realistic reactor geometry; and a technique to deal with the issues of finance, risk assessment, and public perception.

Title List of Documents Made Publicly Available

Title List of Documents Made Publicly Available PDF Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 796

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Atomic Energy and Nuclear Power

Atomic Energy and Nuclear Power PDF Author: United States. Superintendent of Documents
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 40

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