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Material Challenges for Corrosive Environments and High Temperatures in Lead-Cooled Fast Reactor Janah, Yulia Miftah Hul; Angelina, Tsania Eksa; Mustari, Asril Pramutadi Andi
Indonesian Journal of Physics Vol 35 No 2 (2024): Vol 35 No 2 2024
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.5614/itb.ijp.2024.35.2.3

Abstract

Research on one of the generation IV reactors, the Lead-Cooled Fast Reactor (LFR), began in the 1950s. The development of this reactor continues until now. However, there are material challenges in the development of LFR. LFR coolant that uses liquid Pb or Pb-Bi is one of the challenges in this reactor because it causes severe corrosion. Researchers have tested various materials such as steel, ceramics, composites, and refractory alloys in liquid Pb or Pb-Bi environments to assess their corrosion resistance. These materials have shown improved radiation performance at high temperatures and have been developed (such as ODS, FeCrAl, SS316, AISI 316 EP823, AISI 304, and HCM12A). However, these materials are not yet sufficiently compatible with corrosion performance. The results indicate that no metal or ceramic material currently proves to be completely resistant to corrosion and radiation over the long term. The LFR system is intriguing but has limited applicability until suitable construction material designs are further identified.
Simulation of Three Points Bending SS316 to Know Mechanical Stress with ABAQUS Janah, Yulia Miftah Hul; Mustari, Asril Pramutadi Andi
Indonesian Journal of Physics Vol 35 No 2 (2024): Vol 35 No 2 2024
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.5614/itb.ijp.2024.35.2.1

Abstract

The operating life of the Gen IV nuclear reactor, which is 60 years, will require material upgrades over a very long period of time. Stability, high reliability, adequate resources, and easy fabrication, as well as weldability, environmental impact, and aging, are other important aspects to consider during the material selection process. SS316 is currently in demand as a structural material for future Gen IV nuclear power plants operating at high temperatures. Although grade SS316 has been studied for current nuclear service conditions and other conventional applications, better data and models for long-term high-temperature properties are needed, especially with regard to primary to tertiary creep strain and creep-fatigue response. The three-point bending test on SS316 material can be modeled with ABAQUS simulation. The purpose of this study is to compare the distribution of the voltage profile for parameters at room temperature (25°C) and high temperature (650°C). In addition, simulations were conducted to compare the effects of load displacement (U2) variations, namely 25, 20 and 15 for each temperature. ABAQUS is an engineering simulation program based on finite element methods that can solve simple linear analysis problems to complex nonlinear simulations. ABAQUS comes with a comprehensive database of elements that can model almost any geometry. This simulation can describe the voltage profile that is spread over the geometry after the required parameters are entered. From the results obtained, the greater the displacement of U2, the smaller the maximum stress that can be resisted by the material. It also shows that at higher temperatures (650°C), materials tend to experience a decrease in strength or maximum stress compared to lower temperatures (25°C). So the material under test experiences a decrease in maximum strength or stress as the temperature increases and the U2 displacement.