In-Service Evaluation of French Pressurized Water Reactor Vessel Steel

Brillaud, C; Hedin, F

doi:10.1520/stp17859s

Cited by 18 publications

(9 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Age hardening is an irradiation-enhanced formation of copper-rich precipitates. These two hardening mechanisms cause an increase of the yield strength whereas phosphorous segregation causes grain boundaries embrittlement without any increase of hardness and may be responsible for intergranular fracture [19]. It should be underlined that the micromechanical models developed in this study do not consider the embrittlement of the grain boundaries due to phosphorous segregation.…”

Section: Effect Of Neutron Irradiation On the Charpy Transition Curvementioning

confidence: 88%

“…This will lead to higher computed stresses. Considering both the impact and fracture toughness properties, it is well known that irradiation embrittlement induces an increase of the DBT temperature and therefore of the index ) 2 1 2 3 [ 2,17,19,23,28,31]. As far as the upper shelf energy (USE) is concerned, most of the studies report a decrease with increasing irradiation level.…”

Section: ¡ E ¥mentioning

confidence: 99%

“…is used in the American regulations. Based on the experimental values given in [14,19,21,32] where only A533B and A508 Cl.3 structural steels are considered linear correlations between showing that the hardening rate is slightly decrease with increasing level of irradiation. 4 [21] [32] [14] ¢ correlation will be considered as the reference experimental database to which the predictions developed in this study for Charpy tests will be compared.…”

Section: ¡ E ¥mentioning

confidence: 99%

See 2 more Smart Citations

Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

Tanguy¹,

Bouchet²,

Bugat³

et al. 2006

Engineering Fracture Mechanics

View full text Add to dashboard Cite

show abstract

Section: Effect Of Neutron Irradiation On the Charpy Transition Curvementioning

confidence: 88%

Section: ¡ E ¥mentioning

confidence: 99%

Section: ¡ E ¥mentioning

confidence: 99%

See 1 more Smart Citation

Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

Tanguy¹,

Bouchet²,

Bugat³

et al. 2006

Engineering Fracture Mechanics

View full text Add to dashboard Cite

show abstract

“…Generally the materials conform to A508 and A533B specifications, (y0?5%Mo, y1?5%Mn and y0?7%Ni) but some of the earlier RPVs were fabricated with Mn-Mo materials of low Ni level (A302B). Surveillance data 59 show welds with three compositional ranges: (i) welds with 0?07-0?10%Ni and 1?31-1?58%Mn from the early stations (Chooz A, Fessenheim 1 and 2 and Bugey 1 and 2). Some doses (wt 1 ) for exposures at 255uC were corrected to effective doses (wt 2 ) at 286uC using the F T parameters (equation ( 7)) at 255 and 286uC and the expression wt 2 5wt 1 {F T255 /F T286 } 2 (ii) welds with 0?49-0?57%Ni and 1?50 The available results for the welds from group (iii) were insufficient for regression analysis but fell within the scatter of the first two weld sets.…”

Section: Surveillance and Accelerated Irradiation Data For Mn-mo Stee...mentioning

confidence: 99%

Influence of manganese on mechanical properties, irradiation susceptibility and microstructure of ferritic steels, alloys and welds

Jones¹

2011

International Materials Reviews

View full text Add to dashboard Cite

The ferritic steels used world wide for nuclear pressure vessels and irradiated structures contain manganese but knowledge of the role of manganese is mainly confined to the unirradiated condition. Information from the mid 1950s to 2009 on the influence of manganese on unirradiated and irradiated properties is analysed. In unirradiated material manganese raises ambient strength, improves notched impact toughness, benefits high temperature strength, promotes dynamic strain aging and enhances creep resistance. However, by combining with carbon and by increasing phosphorus diffusion, manganese increases intergranular embrittlement after thermal aging. Neutron irradiated steels are deleteriously affected by manganese. First, the dose coefficients of irradiation hardening and embrittlement increase linearly with manganese, particularly in steels with uncombined nitrogen, and the morphology of irradiation induced interstitial loops is altered. Second, manganese occurs in irradiation induced Cu rich precipitates, altering their morphology and the associated hardening. Third, manganese becomes incorporated into irradiation enhanced Cu-Ni-Mn precipitates and Mn-Ni-Si nanoclusters that increase hardening and embrittlement at high doses. Finally, manganese segregates at grain boundaries under irradiation. Overall, the unirradiated benefits are outweighed by deleterious irradiation effects. These factors are important in supporting continued reactor operations, extending lifetimes of existing nuclear vessels and structures, improving steel specifications for advanced reactors and developing steels for nuclear fusion applications.

show abstract

“…The most common features observed as a result of fast neutron radiation damage in RPV steels are voids, dislocation loops, and solute clusters composed primarily of Si, Ni, Mn and Cu [3][4][5][6]. The latter is the focus of a global research effort to gain a mechanistic understanding of solute clustering in RPV steels [7][8][9][10][11][12][13][14][15][16]. The aim of this global effort is two-fold, to improve the design of new steel compositions, especially their resistance to radiation-induced solute clustering, and improving current dose damage relationship models at high fluences beyond 40 years operation of a PWR.…”

Section: Introductionmentioning

confidence: 99%

Understanding the importance of the energetics of Mn, Ni, Cu, Si and vacancy triplet clusters in bcc Fe

Whiting

Burr

King

et al. 2019

Journal of Applied Physics

View full text Add to dashboard Cite

Numerous experimental studies have found the presence of (Cu)-Ni-Mn-Si clusters in neutron irradiated reactor pressure vessel steels, prompting concerns that these clusters could lead to larger than expected increases in hardening, especially at high fluences late in life. The mechanics governing clustering for the Fe-Mn-Ni-Si system are not well-known; state-of-the-art methods use kinetic Monte Carlo (KMC) parameterised by density functional theory (DFT) and thermodynamic data to model the time evolution of clusters. However, DFT based KMC studies have so far been limited to only pairwise interactions due to lack of DFT data. Here we explicitly calculate the binding energy of triplet clusters of Mn, Ni, Cu, Si and vacancies in bcc Fe using DFT to show that the presence of vacancies, Si, or Cu stabilises cluster formation, as clusters containing exclusively Mn and/or Ni are not energetically stable in the absence of interstitials. We further identify which clusters may be reasonably approximated as a sum of pairwise interactions, and which instead require an explicit treatment of the three-body interaction, showing that the three-body term can account for as much as 0.3 eV, especially for clusters containing vacancies.

show abstract

In-Service Evaluation of French Pressurized Water Reactor Vessel Steel

Cited by 18 publications

References 0 publications

Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

Influence of manganese on mechanical properties, irradiation susceptibility and microstructure of ferritic steels, alloys and welds

Understanding the importance of the energetics of Mn, Ni, Cu, Si and vacancy triplet clusters in bcc Fe

Contact Info

Product

Resources

About