Development of Innovative Reactor Assembly Components towards Commercialization of Future FBRs

Chellapandi, P.; Puthiyavinayagam, P.; Balasubramaniyan, V.; Raghupathy, S.; Babu, V. Rajan; Chetal, S.C.; Raj, Baldev

doi:10.1016/j.egypro.2011.06.047

Cited by 9 publications

(3 citation statements)

References 1 publication

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“…However, the compressive stress acting on the hardfaced deposit is around 15 MPa only, which is very much less than the yield stress of the deposit. Hence, the hardfaced deposit is very safe due to compressive stress [10]. Table 1 shows the process parameters for hardfacing by PTAW for lower dilution and finer microstructure so that maximum hardness of the coating can be achieved [11].…”

Section: Significance Of the Studymentioning

confidence: 99%

Effects of Different Operating Temperatures on the Tensile Properties of the Grid Plate Hardfaced with Colmonoy in a Pool Type Sodium Fast Reactor

Balaguru¹,

Vela

Chellapandi

2017

Science and Technology of Nuclear Installations

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In sodium-cooled fast reactors (SFRs), the grid plate is a critical component which is made of 316 L(N) SS. It is supported on a core support structure which is also made of 316 L(N) SS. This assembly is immersed in a pool of sodium which acts as a coolant. If there is a direct contact between the grid plate and the flange of core support structure, self-welding takes place between them at the high operating temperature of SFR by a thin sheet of liquid sodium which gets into the gap between them as this sodium acts as a metallic gum. To avoid self-welding, the bottom plate of the grid plate is hardfaced with Colmonoy 5 by PTAW so that the direct contact between those two components is avoided. Due to the difference in coefficients of thermal expansion between the base metal and the coating, the interface is subjected to tensile force which may weaken the bonding strength between them at higher temperatures. Therefore, the weldment should be able to withstand the tensile force at higher operating temperatures for which hot tensile properties of the base metal and the weldment have been determined to study the compatibility between them after hardfacing for the reliable operation of SFR.

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Section: Significance Of the Studymentioning

confidence: 99%

Effects of Different Operating Temperatures on the Tensile Properties of the Grid Plate Hardfaced with Colmonoy in a Pool Type Sodium Fast Reactor

Balaguru¹,

Vela

Chellapandi

2017

Science and Technology of Nuclear Installations

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“…Considering the geometrical configuration of roof slab of nuclear reactor, the large box-type structure with many penetrations made of carbon steel posed many difficulties during manufacturing, in particular, due to lamellar tearing. Alternatively, taking advantage of high load carrying capacity with possibly minimum thickness, a dome-shaped roof slab was conceived which comprised a conical shell connected to the vertical shell through a short torus portion [2].…”

Section: Introductionmentioning

confidence: 99%

“…Structural integrity refers to the condition of a structural system and implies that the structure and its components remain intact over the intended lifetime of the structure. The roof slab is subjected to fatigue loading due to the reaction taking place inside the main vessel and due to the intermittent flow of sodium [2]. The fatigue phenomenon is a complex and progressive failure and one possibility of occurrence could be from a small weld defect present locally in the weldments.…”

Section: Introductionmentioning

confidence: 99%

Reliability-Based Design Optimization of Pump Penetration Shell Accounting for Material and Geometric Non-Linearity

Velayudhan

Venugopal

Thankareathenam

et al. 2021

SV-JME

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The roof slab of the nuclear reactor supports all the components and sub-systems. Roof slab needs to resist the seismic loads in accordance with load-carrying criteria. The static stress analysis of the reactor roof slab reveals that high-stress concentration was present in the pump penetration shell (PPS) which supports the primary sodium pump. This paper presents the assessment of collapse load and optimization of pump penetration shell, through the reliability approach, accounting for material nonlinearity, geometrical nonlinearity and randomness in loading. In addition to that, the load-carrying capacity of PPS was determined considering two different materials, viz., IS2062 and A48P2. The design of experiments (DoE) was formulated considering the flange angle and flange thickness as parameters. An empirical model for load function was formulated from the results of the collapse load obtained for various combinations of design parameters. The above function was used to perform the reliability-based geometry optimization of PPS of the roof slab.

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Experimental and Numerical Prediction of Fatigue Behavior of Ring Type Specimen

Prabhu¹,

Ebron²,

Gautham³

et al. 2020

Lecture Notes in Mechanical Engineering

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Development of Innovative Reactor Assembly Components towards Commercialization of Future FBRs

Cited by 9 publications

References 1 publication

Effects of Different Operating Temperatures on the Tensile Properties of the Grid Plate Hardfaced with Colmonoy in a Pool Type Sodium Fast Reactor

Effects of Different Operating Temperatures on the Tensile Properties of the Grid Plate Hardfaced with Colmonoy in a Pool Type Sodium Fast Reactor

Reliability-Based Design Optimization of Pump Penetration Shell Accounting for Material and Geometric Non-Linearity

Experimental and Numerical Prediction of Fatigue Behavior of Ring Type Specimen

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