Structural and mechanical properties of different types of graphite used in nuclear applications

Kurpaska, Ł.; Frelek-Kozak, M.; Wilczopolska, Magdalena; Bonicki, W.; Diduszko, R.; Zaborowska, A.; Wyszkowska, E.; Clozel, M.; Kosińska, A.; Cieślik, Iwona; Duchna, Monika; Jóźwik, I.; Chmurzynski, W.; Olszewski, G. B.; Zając, Bogdan; Jagielski, J.

doi:10.1016/j.molstruc.2020.128370

Cited by 8 publications

(7 citation statements)

References 33 publications

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“…The medium fluence of heavy Ar + ions already caused a reduction of crystallites to the minimum value of 10 -15 nm. In the case of light He + ions damage at 1E16 ion/cm 2 is not yet critical. It needs to be mentioned that results of both in-depth and surface analysis are consistened.…”

Section: Resultsmentioning

confidence: 99%

“…Without doubt, the main parameters defining the ability of graphite for the use in a nuclear reactor are its strength, purity, crystallinity and level of structural disorder. However, it is not the case that graphite with the highest purity and large crystallites of high order will have the best functional properties, especially mechanical due to the material anisotropic character [2]. Nevertheless, there is a need for the method of evaluation of the material's structure and its reaction on radiation damage.…”

Section: Introductionmentioning

confidence: 99%

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Surface and in-depth structural changes in nuclear graphite irradiated with noble gases described with Raman imaging

Gawęda¹,

Wilczopolska²,

Suchorab³

et al. 2023

Nuclear Instruments and Methods in Physics Research Section B:

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Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Surface and in-depth structural changes in nuclear graphite irradiated with noble gases described with Raman imaging

Gawęda¹,

Wilczopolska²,

Suchorab³

et al. 2023

Nuclear Instruments and Methods in Physics Research Section B:

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“…After irradiation, the material samples undergo various tests, including scanning electron microscopy (SEM), Raman spectroscopy, and X-ray diffraction. Testing methodology prefi gured for graphite samples is precisely described in another work [9]. Since graphite is an essential material for the construction of HTRs, it was chosen as the initiating one.…”

Section: Introductionmentioning

confidence: 99%

“…Historically, irradiation rigs have been designed and operated in MARIA in the 1970s and 1980s, (GAPISZON, MAK, KRS-M, KAMELEON, and several members of KAMA family) with operating temperatures up to 200C and used for other types of research [9,10]. Unfortunately, the competencies associated with these rigs were mostly lost due to the generation gap after the political turmoil of 1989 and the 30 years of limited interest in nuclear power generation; consequently, they had to be rebuilt with a lot of effort and time for the occasion of the current project.…”

Section: Introductionmentioning

confidence: 99%

Preliminary computational and experimental design studies of the ISHTAR thermostatic rig for the high-temperature reactors materials irradiation

2021

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The Irradiation System for High-Temperature Reactors (ISHTAR) thermostatic rig will be used to irradiate advanced core material samples in conditions corresponding to those prevailing in the high-temperature reactors (HTRs): these conditions include a stable temperature extending up to 1000°C in the helium atmosphere. Computational and experimental studies concerning the design have been conducted, proving the possibility of these conditions’ fulfillment inside the rig while maintaining the safety limits for MARIA research reactor. The outcome is the thermostatic rig design that will be implemented in the MARIA reactor. Appropriate irradiation temperature will be achieved by a combination of electric heating with the control system, gamma heating, and a helium insulation gap with precisely designed thickness. The ISHTAR rig will be placed inside the vertical irradiation channel, which is located in the reactor pool. The device is being developed from scratch at the Nuclear Facilities Operation Department of the National Centre for Nuclear Research as a part of the GOSPOSTRATEG programme.

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“…The porosity with approximately 20% and varying dimensions is formed during manufacturing for gas escaping. The macroscopic dimensions of nuclear graphite undergo 3-4% shrinkage and will increase during high temperature irradiation (Kurpaska et al, 2020). At hightemperature and under neutron irradiation environment porosity of nuclear graphite plays a very important role (Huang et al, 2019).…”

Section: Introductionmentioning

confidence: 99%

Oxidation Behavior and Micro Structure Analysis of Nuclear Graphite Ig-110 at 520℃ Under Air Environment

Herlina

Wicaksono

Rivai

2021

Materials Research Communications

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Graphite IG-110 is a nuclear graphite structural and moderator material that has been used for high temperature gas cooled reactors (HTGR). Under normal operating conditions or accidental entry of air or water (air ingress or water ingress), a nuclear graphite. Therefore, the aim of this study is to investigate the oxidation resistant and microstructure change behavior of graphite IG-110 at high temperature under air environment. The sample of IG-110 was tested using Magnetic Suspension Balance (MSB) to analyze the weight change by in-situ for 420 minutes at a temperature of 520 o C. Morphological and microstructure analysis was carried out by optical microscope, SEM-EDS (Scanning Electron Microscope -Energy Dispersive X-ray Sprectroscope) and XRD (X-Ray Diffractometer). The results showed that Graphite IG-110 has a change in surface structure caused by the reaction of the material with oxygen in air at high temperatures. Furthermore, the crystal size of the material structure was slightly change. However, in general, the corrosion rate of graphite IG-110 at a temperature of 520℃ under the air environment is relatively low. So that if graphite IG-110 is exposed to air at a temperature of 520℃ for several hundred minutes in a nuclear reactor estimated does not suffer serious damage.

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Structural and mechanical properties of different types of graphite used in nuclear applications

Cited by 8 publications

References 33 publications

Surface and in-depth structural changes in nuclear graphite irradiated with noble gases described with Raman imaging

Surface and in-depth structural changes in nuclear graphite irradiated with noble gases described with Raman imaging

Preliminary computational and experimental design studies of the ISHTAR thermostatic rig for the high-temperature reactors materials irradiation

Oxidation Behavior and Micro Structure Analysis of Nuclear Graphite Ig-110 at 520℃ Under Air Environment

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