Implementation of power shape adaption technique for the use of automated fixed in-core probes

Gabriel F. Cuevas Vivas; Walid A. Metwally; John P. Rea; Brian R. Moore; Stephan C. Moen

Implementation of power shape adaption technique for the use of automated fixed in-core probes

Gabriel F. Cuevas Vivas
, Walid A. Metwally
, John P. Rea
, Brian R. Moore
, Stephan C. Moen

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

The use of Automated Fixed In-core Probes (AFIPs) in the Economic Simplified Boiling Water Reactor (ESBWR) designed by GE-Hitachi Nuclear Energy Americas, LLC (GEH) is the culmination of an effort to simplify the power monitoring system and eliminate moving parts. To achieve the planned AFIP implementation, a number of studies are in progress to optimize the power monitoring calculation and the use of a continuous flow of information. The capabilities of the monitoring system that uses a traversing detector inside the core were combined with the fixed nature of the AFIP into the new AFIP-based monitoring system. The ultimate goal is an AFIP-based monitoring system with a sound basis for the power calculation uncertainties as well as a monitoring configuration that assures a high performance of the monitoring functions (e.g. power adaption, calibration of Local Power Range Monitors, (LPRMs)). This paper addresses the interpretation of the detector signal and the use of a reduced number of measured data points in the power monitoring system of a Boiling Water Reactor.

Original language	English
Title of host publication	American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Pages	883-892
Number of pages	10
State	Published - 2009
Externally published	Yes
Event	American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV - Hilton Head Island, SC, United States Duration: Apr 12 2009 → Apr 15 2009

Publication series

Name	American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Volume	2

Conference

Conference	American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV
Country/Territory	United States
City	Hilton Head Island, SC
Period	04/12/09 → 04/15/09

Keywords

Core monitoring system
Gamma thermometer
Power adaption

Cite this

Cuevas Vivas, G. F., Metwally, W. A., Rea, J. P., Moore, B. R., & Moen, S. C. (2009). Implementation of power shape adaption technique for the use of automated fixed in-core probes. In American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV (pp. 883-892). (American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV; Vol. 2).

Cuevas Vivas, Gabriel F. ; Metwally, Walid A. ; Rea, John P. et al. / Implementation of power shape adaption technique for the use of automated fixed in-core probes. American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV. 2009. pp. 883-892 (American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV).

@inproceedings{65309e46dfd94c238a8c66c91cb48944,

title = "Implementation of power shape adaption technique for the use of automated fixed in-core probes",

abstract = "The use of Automated Fixed In-core Probes (AFIPs) in the Economic Simplified Boiling Water Reactor (ESBWR) designed by GE-Hitachi Nuclear Energy Americas, LLC (GEH) is the culmination of an effort to simplify the power monitoring system and eliminate moving parts. To achieve the planned AFIP implementation, a number of studies are in progress to optimize the power monitoring calculation and the use of a continuous flow of information. The capabilities of the monitoring system that uses a traversing detector inside the core were combined with the fixed nature of the AFIP into the new AFIP-based monitoring system. The ultimate goal is an AFIP-based monitoring system with a sound basis for the power calculation uncertainties as well as a monitoring configuration that assures a high performance of the monitoring functions (e.g. power adaption, calibration of Local Power Range Monitors, (LPRMs)). This paper addresses the interpretation of the detector signal and the use of a reduced number of measured data points in the power monitoring system of a Boiling Water Reactor.",

keywords = "Core monitoring system, Gamma thermometer, Power adaption",

author = "\{Cuevas Vivas\}, \{Gabriel F.\} and Metwally, \{Walid A.\} and Rea, \{John P.\} and Moore, \{Brian R.\} and Moen, \{Stephan C.\}",

year = "2009",

language = "English",

isbn = "9781615673513",

series = "American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV",

pages = "883--892",

booktitle = "American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV",

note = "American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV ; Conference date: 12-04-2009 Through 15-04-2009",

}

Cuevas Vivas, GF, Metwally, WA, Rea, JP, Moore, BR & Moen, SC 2009, Implementation of power shape adaption technique for the use of automated fixed in-core probes. in American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV. American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV, vol. 2, pp. 883-892, American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV, Hilton Head Island, SC, United States, 04/12/09.

Implementation of power shape adaption technique for the use of automated fixed in-core probes. / Cuevas Vivas, Gabriel F.; Metwally, Walid A.; Rea, John P. et al.
American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV. 2009. p. 883-892 (American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV; Vol. 2).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Implementation of power shape adaption technique for the use of automated fixed in-core probes

AU - Cuevas Vivas, Gabriel F.

AU - Metwally, Walid A.

AU - Rea, John P.

AU - Moore, Brian R.

AU - Moen, Stephan C.

PY - 2009

Y1 - 2009

N2 - The use of Automated Fixed In-core Probes (AFIPs) in the Economic Simplified Boiling Water Reactor (ESBWR) designed by GE-Hitachi Nuclear Energy Americas, LLC (GEH) is the culmination of an effort to simplify the power monitoring system and eliminate moving parts. To achieve the planned AFIP implementation, a number of studies are in progress to optimize the power monitoring calculation and the use of a continuous flow of information. The capabilities of the monitoring system that uses a traversing detector inside the core were combined with the fixed nature of the AFIP into the new AFIP-based monitoring system. The ultimate goal is an AFIP-based monitoring system with a sound basis for the power calculation uncertainties as well as a monitoring configuration that assures a high performance of the monitoring functions (e.g. power adaption, calibration of Local Power Range Monitors, (LPRMs)). This paper addresses the interpretation of the detector signal and the use of a reduced number of measured data points in the power monitoring system of a Boiling Water Reactor.

AB - The use of Automated Fixed In-core Probes (AFIPs) in the Economic Simplified Boiling Water Reactor (ESBWR) designed by GE-Hitachi Nuclear Energy Americas, LLC (GEH) is the culmination of an effort to simplify the power monitoring system and eliminate moving parts. To achieve the planned AFIP implementation, a number of studies are in progress to optimize the power monitoring calculation and the use of a continuous flow of information. The capabilities of the monitoring system that uses a traversing detector inside the core were combined with the fixed nature of the AFIP into the new AFIP-based monitoring system. The ultimate goal is an AFIP-based monitoring system with a sound basis for the power calculation uncertainties as well as a monitoring configuration that assures a high performance of the monitoring functions (e.g. power adaption, calibration of Local Power Range Monitors, (LPRMs)). This paper addresses the interpretation of the detector signal and the use of a reduced number of measured data points in the power monitoring system of a Boiling Water Reactor.

KW - Core monitoring system

KW - Gamma thermometer

KW - Power adaption

UR - https://www.scopus.com/pages/publications/74549202827

M3 - Conference contribution

AN - SCOPUS:74549202827

SN - 9781615673513

T3 - American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV

SP - 883

EP - 892

BT - American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV

T2 - American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV

Y2 - 12 April 2009 through 15 April 2009

ER -

Cuevas Vivas GF, Metwally WA, Rea JP, Moore BR, Moen SC. Implementation of power shape adaption technique for the use of automated fixed in-core probes. In American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV. 2009. p. 883-892. (American Nuclear Society - 4th Topical Meeting on Advances in Nuclear Fuel Management 2009, ANFM IV).

Implementation of power shape adaption technique for the use of automated fixed in-core probes

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Publication series

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Keywords

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