The helical steam generator is connected to an HTGR-type nuclear reactor called PeLUIt-40 for steam production. Steam is used to generate electricity and hydrogen. A once-through helical tube bundle was employed because of its ability to endure mechanical stress due to thermal expansion, high resistance to flow-induced vibrations, and better thermal performance compared to a straight tube one. To produce the targeted steam, a design analysis of the once-through helical steam generator needs to be conducted. A quick evaluation method was used to predict the preliminary specifications required for steam production. Simple thermodynamic calculations combined with empirical heat transfer coefficients covering convective and boiling processes at constant pressure were used to carry out the analysis. Two scenarios were conducted to evaluate the design choice based on the previous design of RDE-10.
In 2018, BATAN propose detail engineering design of Experimental Power Reactor (RDE). An important issue of RDE is Ceramic Internals or Reactor Pressure Vessel (RPV). Ceramic Internals is pathway of helium gas, control rod, absorber ball and also pebble fuel. Its structural component must sustain by the load of 27000 pebbles fuel. A preliminary static structural analysis of bottom reflector, a part of Ceramic Internals, has been studied before, the result was satisfying and could be scale-up to analyse the Ceramic Internals with same methods. Design and static structural simulation are performed by using Solidworks software to study the factor of safety distribution in Ceramic Internals. The design was made in 16 layers with small dowel as the component to endure the movement. Factor of safety was obtained in static simulation using single simplified parts. The preliminary result show that the minimum factor of safety can handle the load of Ceramic Internals structural. This result show that the model is suitable for RDE design.
The power reactor with high-temperature gas-cooled reactor (HTGR) technology uses uranium as the reactor fuel. The energy from fission is converted to electrical energy or used for other needs such as hydrogen production or other research activities at high temperatures of around 700 °C. This operation does not allow the use of metal as the core material for the reactor. The material that fits the requirements as a core structure is graphite. Graphite material has specific characteristics, namely the parameters of the modulus of elasticity, coefficient of thermal expansion, and the volume which changes due to temperature and neutron dose. Because the structure of the reactor core is a vital component in the reactor, this research will develop a method for the design of the reactor core structure with graphite material. The design method is based on Design by Analysis which specifically refers to the strain analysis on each of the reactor core components. The design method developed is based on the finite element method. The object of this research is the side reflector made from the Toyo Tanso IG-110 series graphite. Based on the analysis of heat distribution and heat stress for the material before the effect of neutron exposure, the temperature distribution on the side reflector was found, as well as the displacement and heat stress that occurs. isotropic properties, Young's modulus and Poisson’s ratio values can be verified and estimated. The purpose of this research is to analyze the strain of the reactor core structure by taking into account the uncertainty of the graphite properties.
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