Analysis of dynamic conditions during thermal transient events for the structural assessment of a nuclear vessel

Ferreño, Diego; Lacalle, R.; Gorrochategui, I.; Gutiérrez‐Solana, F.

doi:10.1016/j.engfailanal.2009.10.024

Cited by 3 publications

(3 citation statements)

References 5 publications

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“…Some examples of successful applications can be found in Refs. [11][12][13][14][15][16]. The main features and advantages of the method are hereafter summarized:…”

Section: The MCmentioning

confidence: 99%

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Structural Integrity Assessment of a Nuclear Vessel through ASME and Master Curve Approaches Using Irradiation Embrittlement Predictions

Ferreño

Fernández-Rucoba²,

Casado

et al. 2020

Journal of Testing and Evaluation

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The assessment of the structural integrity of nuclear vessels is based on a series of procedures developed in the 1970s and 1980s. On one hand, curves that, according to the American Society of Mechanical Engineers code, describe the relationship between steel toughness and temperature in the ductile-to-brittle transition region, based on the reference temperature concept RT NDT , were adopted in 1972. On the other hand, the material embrittlement derived from the exposure of steel to neutron irradiation is determined through the model included in "Regulatory Guide 1.99 Rev. 2," published in 1988. Since then, there have been enormous advances in this field. For example, the Master Curve, based on the reference temperature T 0 , describes the relationship between toughness and temperature in the transition zone more realistically and with much more robust microstructural and mechanical foundations and uses the elastic-plastic fracture toughness K Jc . Moreover, improved models have been developed to estimate the embrittlement of steel subjected to neutron irradiation, such as ASTM E900, Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials. This study is aimed at comparing the results obtained using traditional procedures to the improved alternatives developed later. For this purpose, the behavior of the steel of a nuclear vessel that is currently under construction has been experimentally characterized through RT NDT and T 0 parameters. In addition, the material embrittlement has been quantified using "Regulatory Guide 1.99 Rev. 2" and ASTM E900. These experimental results 4 Equipos Nucleares, S.A., S.M.E. Av.

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“…Some examples of successful applications can be found in Refs. [11][12][13][14][15][16]. The main features and advantages of the method are hereafter summarized:…”

Section: The MCmentioning

confidence: 99%

“…However, the experimental evidence shows that the MC concept can also be applied to dynamic tests [13,14,[19][20][21]. In this sense, Wallin [19] has proposed a simple semiempirical expression for the strain rate dependence of T 0 .…”

Section: The MCmentioning

confidence: 99%

Structural Integrity Assessment of a Nuclear Vessel through ASME and Master Curve Approaches Using Irradiation Embrittlement Predictions

Ferreño

Fernández-Rucoba²,

Casado

et al. 2020

Journal of Testing and Evaluation

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“…The results show that the position where the wall stress is greatest is in the interface between the shell and the container. D. Ferreño [7] numerically simulated the thermal stress process of the reactor pressure vessel, obtained the dynamic reference temperature T 0,dyn , corresponding to the loading rate under thermal shock, and compared it with the quasi-static reference temperature T 0,sta . A. Kandil [8] analyzed the stress distribution of cylindrical pressure vessels under the joint action of steady-state pressure and temperature, and obtained the relationship between average stress and stress amplitude under different operating conditions.…”

Section: Introductionmentioning

confidence: 99%

Analysis of thermal-force coupling stress field under the temperature of alternating of molecular sieve adsorption tower

et al. 2021

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The thermal stress of molecular sieve adsorption tower under transient temperature of 40-290°C is the basis for ensuring the safe operation of the adsorption tower. In this paper, based on the transient thermodynamics theory, the finite element model of the full-size adsorption tower is established. The distribution of thermal stress at the key positions of the tower body is analyzed, and the strength of the maximum equivalent stress position is evaluated. The results show that the maximum residual stress is at the corner of the inner wall of the tower opening to take over the import and export, the maximum is 313.34MPa, and the effect force is gradually diffused along the takeover; The thermal stress on the inside and outside of the skirt is greater than the thermal stress on the inside and outside of the head. The corresponding stress linearization results of each assessment path were evaluated and passed. The strength design, life prediction and maintenance of adsorption tower in complex temperature cross-change conditions provide theoretical basis.

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Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients

Huang

et al. 2023

Annals of Nuclear Energy

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Analysis of dynamic conditions during thermal transient events for the structural assessment of a nuclear vessel

Cited by 3 publications

References 5 publications

Structural Integrity Assessment of a Nuclear Vessel through ASME and Master Curve Approaches Using Irradiation Embrittlement Predictions

Structural Integrity Assessment of a Nuclear Vessel through ASME and Master Curve Approaches Using Irradiation Embrittlement Predictions

Analysis of thermal-force coupling stress field under the temperature of alternating of molecular sieve adsorption tower

Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients

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