Acoustic emission monitoring of hot functional testing: Watts Bar Unit 1 Nuclear Reactor

Hutton, P.H.; Dawson, J.F.; Friesel,; Harris, J.C.; Pappas, R.A.

doi:10.2172/6855591

Cited by 10 publications

(7 citation statements)

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“…The specimen was designed such that the system operating temperature would impose thermal loads and cause crack growth. The test results showed that coolant flow noise can be filtered out, and that the acoustic emission signals from a fracture specimen can be detected under operating conditions [Hutton et al 1984]. Acoustic emission was also used to monitor possible crack growth during the 1987 hydrotest of the High Flux Isotope Reactor located at the Oak Ridge National Laboratory; no evidence of crack growth was detected [Hutton 1989].…”

Section: Acoustic Emission Monitoringmentioning

confidence: 99%

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

Natesan

Shankar²,

Shah³

2007

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The NGNP, which is an advanced HTGR concept with emphasis on both electricity and hydrogen production, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000°C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the VHTR can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K.This report has reviewed the available information on candidate materials for the construction of RPV and has made a preliminary assessment of several relevant factors to make a judicious selection of the material for the RPV. Some of the factors addressed in this report are availability of commercial alloys for RPV application, their status in ASME Codes for nuclear service, ASME code compliance during steady state and depressurized conduction cooling conditions, baseline mechanical properties, effects of thermal aging on mechanical properties and code compliance over long term, fabrication and welding issues, global assessment of availability/capability of vendors for RPV procurement, and technology gaps in our knowledge base to address some of the technical issues. The assessment included three primary candidate alloys namely, low alloy steel SA508 (UNS K12042), Fe-2.25Cr-1Mo-0.25V steel (UNS K31835), and modified 9Cr-1Mo steel (UNS K90901) for the RPV. Several conclusions were drawn from this assessment:Baseline Mechanical Properties: There is sufficient database available for the mechanical properties of SA-508 steel. There is limited data available on the thermal aging effects on the mechanical properties and additional information needs development on the long-term aging effects. The steel is approved for use up to 371°C (700°F) under the ASME Code. At present no data is available on the effects of impure helium on the long-term corrosion and mechanical properties of the material.There is adequate tensile data on the Fe-2.25Cr-1Mo-0.25V in the temperature range of interest in NGNP RPV. There is only limited creep data available for the steel and additional data are needed, especially at elevated temperatures that encompass depressurized conduction cooldown conditions. However, substantial data on the creep fatigue properties, thermal aging affects on the mechanical properties, performance characteristics in impure helium, and properties of thick section material are needed prior to its selection for NGNP RPV. Furthermore, the steel is approved under ASME Code Section VIII (for non nuclear applications) and is not approved under Section III for use in nuclear systems.Substantial database on the baseline mechanical properties is currently available for the Modified 9Cr-1Mo steel. Sufficient data are also avail...

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Section: Acoustic Emission Monitoringmentioning

confidence: 99%

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

Natesan

Shankar²,

Shah³

2007

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“…AE relies on the (usually long-range) detection of stress waves that emanate from damage sites, either intrinsically due to the growth process of the damage or as a result of an external applied load to the 4.4 component. AE is well suited for online monitoring of passive components in nuclear power plants, and has been applied for crack growth detection (Harris and Dunegan 1974;Hutton et al 1984;Hutton 1993;Hutton et al 1993;Ai et al 2010;Meyer et al 2011b), leak detection (IAEA 2008b), and loose part monitoring (IAEA 2008b). GW also relies on the interaction of long-range stress waves with damage in the component (Rose 1999;Meyer et al 2012b).…”

Section: Data Collection -Nde For Passives Variable Sensing For Activesmentioning

confidence: 99%

“…A number of studies on the use of AE for monitoring nuclear components have been performed, and applications include crack growth monitoring, leak detection, and loose part detection and monitoring (Harris and Dunegan 1974;Hutton et al 1984;Hutton 1993;Hutton et al 1993;IAEA 2008b;Ai et al 2010;Meyer et al 2011b). AE was also deployed for a limited field trial to monitor the growth of cracks in two RPV nozzles at Limerick Generating Station Unit 1 (BWR) reactor and the Watts Bar Unit 1 (PWR) reactor (Hutton et al 1991;Hutton et al 1993).…”

Section: Metalsmentioning

confidence: 99%

Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications

Coble¹,

Ramuhalli²,

Bond³

et al. 2012

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Recent years have seen a resurgence of nuclear power worldwide, with interest in extending the operating life of the approximately 436 reactors currently in service (as of March, 2012), 61 new reactors being constructed, and as many as 162 under consideration. Renewed worldwide interest in nuclear power has been somewhat tempered by the March 2011 incident at Fukushima Dai-ichi in Japan. However, nuclear power is still considered a key element in meeting future worldwide sustainable energy, energy security, and emissions goals. Currently, three separate thrusts to safe and economical nuclear power development for energy security are being pursued in the United States: (i) longer term operation for the legacy fleet, from 40-60 and possibly 60-80 years; (ii) near-term new nuclear plants with a 60-year design life; and (iii) small modular reactors, which are expected to employ light water reactor technology at least in the medium term. Within these activities, attention is turning to enhanced methods for plant component and structural health management.The operating U.S. fleet includes 104 light water reactors. In addition, there are now (as of May 2012) four new nuclear power plants (AP-1000 plants) under construction in the United States, and two delayed plants are being completed by the Tennessee Valley Authority. There is also interest in the United States in small modular reactors (SMRs), which could be easier to match to existing grid infrastructure and which could replace aging coal fired plants. The current low price for natural gas presents a challenge to the economics of nuclear power, at least in the short term; however, some recent studies have demonstrated that nuclear generation will be competitive in the longer term (at least in some markets) when anticipated escalation in gas prices and the cost of building, operating, and maintaining gas-fired plants are considered over those same time periods.This report reviews the current state of the art of prognostics and health management (PHM) for nuclear power systems and related technology currently applied in field or under development in other technological application areas, as well as key research needs and technical gaps for increased use of PHM in nuclear power systems. The historical approach to monitoring and maintenance in nuclear power plants (NPPs), including the Maintenance Rule for active components and Aging Management Plans for passive components, are reviewed. An outline is given for the technical and economic challenges that make PHM attractive for both legacy plants through Light Water Reactor Sustainability (LWRS) and new plant designs. There is a general introduction to PHM systems for monitoring, fault detection and diagnostics, and prognostics in other, non-nuclear fields. The state of the art for health monitoring in nuclear power systems is reviewed. A discussion of related technologies that support the application of PHM systems in NPPs, including digital instrumentation and control systems, wired and wireless sensor techno...

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“…На третьому етапі АЕ-моніто-ринг проводили на діючому реакторі Watts Bar Unit 1 як під час гідростатичних передексплу-атаційних випробувань, так і під час пуску ре-актора та його роботи. Задля кількісної оцінки параметрів АЕ-сигналів та ефективної локації джерел АЕ здійснювали окрему процедуру калі-брування каналів АЕ-системи із використанням АЕ-імітаторів [26].…”

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“…До пе-реліку завдань, поставлених для досліджень, на-лежить розпізнавання сигналів АЕ, які є характер-ними тільки для росту тріщини та встановлення кореляцій між параметрами сигналів АЕ та роз-витком руйнування [15][16][17][18][19][20][21][22][23][24][25][26][27].…”

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Application Of Acoustic Emission Method For Diagnostics Of Nuclear Reactor Bodies (review). Information Ii. Method Of Acoustic Emission In Diagnostics Of Npp Reactor Bodies. Part 2

Neklyudov¹,

Nazachuk²,

Skal’skii³

et al. 2015

Tekh. Diagnost. i Nerazrush. Kontrol

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Acoustic emission monitoring of hot functional testing: Watts Bar Unit 1 Nuclear Reactor

Cited by 10 publications

References 0 publications

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications

Application Of Acoustic Emission Method For Diagnostics Of Nuclear Reactor Bodies (review). Information Ii. Method Of Acoustic Emission In Diagnostics Of Npp Reactor Bodies. Part 2

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