Issues for Nuclear Power Plants Steam Generators

Bonavigo, Lucia; Salve, Mario De

doi:10.5772/14853

Cited by 7 publications

(3 citation statements)

References 11 publications

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“…Nonetheless, the heat-exchange tubes must be washed also in horizontal steam generators. [Bonavigo andDe Salve 2011, Trunov et al 2008] 2.5 Neutronic differences between LEU and MOX fuels…”

Section: Steam Generatormentioning

confidence: 99%

Comparison of Methods for Calculating the Neutronic Characteristics of a VVER-1200 Fuel Assembly

Lavronenko

Savankov

Vnukov

et al. 2022

YadEn

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“…Nonetheless, the heat-exchange tubes must be washed also in horizontal steam generators. [Bonavigo andDe Salve 2011, Trunov et al 2008] 2.5 Neutronic differences between LEU and MOX fuels…”

Section: Steam Generatormentioning

confidence: 99%

Comparison of Methods for Calculating the Neutronic Characteristics of a VVER-1200 Fuel Assembly

Lavronenko

Savankov

Vnukov

et al. 2022

YadEn

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“…There are few steam generator designs depending on the type of the nuclear power plant [1]. Here, it is necessary to mention that the discussion inside the chapter is focused solely on heat exchangers in the so-called pressurized water reactor (PWR) NPPs where both the primary and secondary fluids are water.…”

Section: Introductionmentioning

confidence: 99%

Operation and Performance Analysis of Steam Generators in Nuclear Power Plants

Šadek¹,

Grgić²

2017

Heat Exchangers - Advanced Features and Applications

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Steam generators are components in which heat produced in the reactor core is transferred to the secondary side, the steam supply system, of the nuclear power plant (NPP). Steam generators (SGs) have to fulfil special nuclear regulatory requirements regarding their size, selection of materials, pressure loads, impact on the NPP safety, etc. The primary-side fluid is liquid water at the high pressure, and the fluid on the secondary side is saturated water-steam mixture at the pressure twice as low. A special attention is given to preserving the boundary between the contaminated water in the primary reactor coolant system and the water-steam mixture in the secondary system. A brief overview of the SG design, its operation and the mathematical correlations used to quantify heat transfer is given in the chapter. Results of the SG transient behaviour obtained by the simulation with the best-estimate computer code RELAP5, developed for safety analyses of NPPs, are also presented. Two types of steam generators are analyzed: the inverted U-tube SG, which is commonly found in the present-day pressurized water reactors and the helicalcoil SG that is part of the new-generation reactor designs.

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“…The reliability and performance of steam generators are crucial in pressurized water nuclear power plants, because the tubes in the steam generator are the barriers between the highly radioactive primary coolants and the uncontaminated secondary coolants, and should transfer the heat of the primary coolants to the secondary coolants efficiently [1]. Thus, the nuclear regulation authority requires that the tubes are inspected periodically, typically using eddy-current testing methods, to determine if there are any defects such as cracks inside [2].…”

Section: Introductionmentioning

confidence: 99%

A Mobile Robotic System for the Inspection and Repair of SG Tubes in NPPs

Seo

Jeong

Shin

et al. 2016

International Journal of Advanced Robotic Systems

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The reliability and performance of a steam generator (SG) is one of the serious concerns in the operation of pressurized water nuclear power plants. Because of high levels of radiation, robotic systems have been used to inspect and repair SG tubes. In this paper, we present a mobile robotic system that positions the inspection and repair tools while hanging down from the tube sheets where the tubes are fixed. All of the driving mechanisms of the mobile robot are actuated by electric motors to start its works, providing that the electric power is prepared without the additional need for an on-site air services. A special tube-holding mechanism with a high holding force has been developed to prevent falling from the tube sheets, even in the case of an electric power failure. We have also developed a quick installation guide device that guides the mobile robot to desired initial positions in the tube sheet exactly and quickly, which helps to reduce the radiation exposure of human workers during the installation work. This paper also provides on-site experimental results and lessons learned.

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Issues for Nuclear Power Plants Steam Generators

Cited by 7 publications

References 11 publications

Comparison of Methods for Calculating the Neutronic Characteristics of a VVER-1200 Fuel Assembly

Comparison of Methods for Calculating the Neutronic Characteristics of a VVER-1200 Fuel Assembly

Operation and Performance Analysis of Steam Generators in Nuclear Power Plants

A Mobile Robotic System for the Inspection and Repair of SG Tubes in NPPs

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