Development of a Noise-based Method for the Determination of the Moderator Temperature Coefficient of Reactivity (MTC) in Pressurized Water Reactors (PWRs) PDF Download

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Development of a Noise-based Method for the Determination of the Moderator Temperature Coefficient of Reactivity (MTC) in Pressurized Water Reactors (PWRs)

Development of a Noise-based Method for the Determination of the Moderator Temperature Coefficient of Reactivity (MTC) in Pressurized Water Reactors (PWRs) PDF Author: Chalmers tekniska högskola
Publisher:
ISBN: 9789172912243
Category :
Languages : en
Pages : 72

Book Description

Development of a Noise-based Method for the Determination of the Moderator Temperature Coefficient of Reactivity (MTC) in Pressurized Water Reactors (PWRs)

Development of a Noise-based Method for the Determination of the Moderator Temperature Coefficient of Reactivity (MTC) in Pressurized Water Reactors (PWRs) PDF Author: Chalmers tekniska högskola
Publisher:
ISBN: 9789172912243
Category :
Languages : en
Pages : 72

Book Description

Development of a Standard for Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity in Water-moderated Power Reactors

Development of a Standard for Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity in Water-moderated Power Reactors PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

Book Description
The moderator temperature coefficient of reactivity (MTC) is an important parameter in safety analyses for thermal reactors. A positive MTC can exacerbate the severity of heatup transients, while a negative MTC can worsen the severity of cooldown transients. In particular, a strongly negative MTC is the major determinate of the severity of the steamline-break accident for pressurized water reactors (PWRs). Conversely, positive and negative MTCs can mitigate the severity of cooldown and heatup transients, respectively. Consequently, the accurate measurement and prediction of MTCs is an important factor in demonstrating that power reactors can be operated safely. ANS 19.11, the standard for ''Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity in Water-Moderated Power Reactors, '' recently has been approved as a national standard by the American National Standards institute (ANSI) and the American Nuclear Society (ANS). At present, the scope of the standard is limited to PWRs, because that is the only type of power reactor currently sited in the US for which measurement of the MTC is required. The standard addresses the calculation and measurement of the MTC, and it also addresses the calculation of the ITC.

American National Standard

American National Standard PDF Author: American Nuclear Society. Standards Committee Working Group ANS-19.11
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages :

Book Description
This standard provides guidance and specifies criteria for determining the MTC in PWRs. Measurement of the isothermal temperature coefficient of reactivity (ITC) at hot-zero-power (HZP) conditions is covered in ANSI/ANS-19.6.1-2011 (R2016). This standard therefore addresses the calculation of the ITC at HZP and the calculation and measurement of the MTC at power. This standard addresses the calculation and measurement of the MTC only in PWRs because that is the only type of power reactor currently sited in the United States for which measurement of the MTC is required.

Development of a Standard for the Moderator Temperature Coefficient of Reactivity in Water-moderated Power Reactors

Development of a Standard for the Moderator Temperature Coefficient of Reactivity in Water-moderated Power Reactors PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

Book Description
The moderator temperature coefficient of reactivity (MTC) is an important parameter in safety analyses for thermal reactors. A positive MTC can exacerbate the severity of heatup transients, while a negative MTC can worsen the severity of cooldown transients. In particular, a strongly negative MTC is the major determinate of the severity of the steamline-break accident for pressurized water reactors (PWRs). Conversely, positive and negative MTCs can mitigate the severity of cooldown and heatup transients, respectively. Consequently, the accurate measurement and prediction of MTCs is an important factor in demonstrating that power reactors can be operated safely. This document discusses the development of a standard for measuring MTC.

Determination of Moderator Temperature Coefficient in a Pressurized Water Reactor Using Neutron and Temperature Noise Analysis

Determination of Moderator Temperature Coefficient in a Pressurized Water Reactor Using Neutron and Temperature Noise Analysis PDF Author: Clinton Eugene Gross
Publisher:
ISBN:
Category :
Languages : en
Pages : 49

Book Description

Validation of Noise Analysis Techniques for Evaluating the Moderator Temperature Coefficient in Pressurized Water Reactors

Validation of Noise Analysis Techniques for Evaluating the Moderator Temperature Coefficient in Pressurized Water Reactors PDF Author: Nikhil Venkatesh
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 186

Book Description

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 : 662

Book Description

INIS Atomindex

INIS Atomindex PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 550

Book Description

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1018

Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

Advances in Nuclear Science and Technology

Advances in Nuclear Science and Technology PDF Author: Jeffery Lewins
Publisher: Springer Science & Business Media
ISBN: 0306470888
Category : Technology & Engineering
Languages : en
Pages : 180

Book Description
Since its initiation in 1962, this series has presented authoritative reviews of the most important developments in nuclear science and engineering, from both theoretical and applied perspectives. In addition, many original contributions are included.
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