Improved Mechanical Properties of the A 508 Class 3 Steel for Nuclear Pressure Vessel Through Steelmaking

Kim, Jeong-Tae; Kwon, Hee-Kyung; Kim, Kook-Chul; Kim, Joong-Myoung

doi:10.1520/stp16590s

Cited by 4 publications

(1 citation statement)

References 4 publications

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“…Because of the thickness of the wall of the vessel, the cooling rate during the quench varies from few tens of degrees per minutes in the centre to few degrees per second at the vicinity of the surface of the shell [1]. In addition, macro and micro segregation inherited of the solidification of the ingot modify locally the chemical composition of the steel [2]. Welding of the different parts of the vessel and the cladding deposit in the inner face introduce different heat affected zones (HAZ) with coarse and refined grains.…”

Section: Introductionmentioning

confidence: 99%

Effect of the bainitic and martensitic microstructures on the hardening and embrittlement under neutron irradiation of a reactor pressure vessel steel

Marini

Averty

Wident

et al. 2015

Journal of Nuclear Materials

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eS789 the experienced raters was found to be 0.48 with a novice rater ICC of 0.48 as well. The ICC between all the raters was 0.33. Conclusion(s):This constitutes poor reliability. The poor reliability of the technique testing the length of LD was identified and addressed in order for adequate usage thereof, in research and in practice. Recommendations of a new technique to test the length of LD were provided by the researcher.A suggestion was made regarding a manner of testing its reliability.Implications: A reliable technique for assessing the length of the Latissimus Dorsi muscle will add to objectivity and consistency in the assessment as well as the management of human movement related musculo-skelatal conditions.

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Section: Introductionmentioning

confidence: 99%

Effect of the bainitic and martensitic microstructures on the hardening and embrittlement under neutron irradiation of a reactor pressure vessel steel

Marini

Averty

Wident

et al. 2015

Journal of Nuclear Materials

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Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels

Altstadt

Bergner

Houška

2021

Nuclear Materials and Energy

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Master Curve Characterization of Irradiation Embrittlement Using Standard and 1/3-Sized Precracked Charpy Specimens

B-S

Yang

Huh

et al. 2001

Effects of Radiation on Materials: 20th International Symposium

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Cleavage initiation fracture toughness (KJC) tests have been performed in the transition temperature ranges of five different heats of reactor pressure vessel steels. The main purpose of this study is to investigate the applicability of the ASTM Standard Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range (E1921-97) to small specimens available in normal surveillance capsules. Precracked Charpy-type specimens with the standard size (10×10×55mm, PCVN) and 1/3-size (3.3×3.3×18.3mm, 1/3-PCVN) are mainly investigated. Results from more than 300 fracture toughness test data are presented including 120 unirradiated PCVN specimens and 100 unirradiated 1/3-PCVN specimens in addition to some CT specimen data and two sets of irradiated PCVN data. The test materials are the IAEA reference steels, so-called JRQ and JFL, and three Korean SA508-3 forging steels that were made by different refining processes. JRQ and a Korean steel, SKA-1, are also evaluated after neutron irradiation by PCVN specimens as well as Charpy impact tests. Fracture toughness data showed that the master curve and its probabilistic bound lines represent the population of the test data measured from different materials and specimens with good accuracy. However, there are still the effects of specimen geometry and size on the measured To values. These effects seem to be more significant in microscopically less homogeneous materials. Smaller bend type specimens may give slightly less conservative results than the larger CT type specimens. One of the important findings is that ultra small 1/3-PCVN specimens are also valuable as the standard size PCVN specimens for determining reference temperatures since the differences are rather systematic and predictable. The T28J correlation, based on the PCVN data only, works well for the current data sets including irradiated materials.

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Improved Mechanical Properties of the A 508 Class 3 Steel for Nuclear Pressure Vessel Through Steelmaking

Cited by 4 publications

References 4 publications

Effect of the bainitic and martensitic microstructures on the hardening and embrittlement under neutron irradiation of a reactor pressure vessel steel

Effect of the bainitic and martensitic microstructures on the hardening and embrittlement under neutron irradiation of a reactor pressure vessel steel

Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels

Master Curve Characterization of Irradiation Embrittlement Using Standard and 1/3-Sized Precracked Charpy Specimens

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