bluuebunny/crossref_metadata_2025_split huggingface dataset:
Study on grain size control technology of 304L austenitic stainless steel
Authors: Wang Y , Sun D D , Bai Y P , Pang Z X 
Published: October 2021

Abstract
In order to solve the problem of mischcrystal in 304L stainless steel with thickness of over 40mm, a series of critical process parameter were studied in laboratory and trial product, such as rolling cycle, temperature of recrystallization controlled rolling, holding time and cooling mode after rolling. The results show that the deformation at 1050°C and 950°C has no significant effect on the recrystallization ratio. The steel plate was dephosphorized by descaling box after the steel was taken out of the heating furnace. After three passes of longitudinal rolling, the steel plate was turned to cross rolling. Before the cross rolling, the surface of the middle slab was dephosphorized, while the remaining passes were not dephosphorized. Static recrystallization could be completed after a short time of warming. The effects of temperature and time on grain growth were compared under the same deformation conditions, it is found that temperature is a sensitive factor for grain growth. The higher the temperature is, the process of recrystallization and grain growth almost happens at the same time. The lower the temperature, the higher the proportion of recrystallization can be maintained, and the abnormal grain growth can be inhibited, which can effectively improve the problem of mischcrystal.
Numerical simulation analysis of tunnel construction mechanical response considering shotcrete hardening process
Authors: Nie Z H , Jin X G , Luo W 
Published: October 2021

Abstract
At present, tunnel construction mechanics studies basically do not consider the hardening process of shotcrete. In order to reveal the hardening process of sprayed concrete in a sulfate environment and the influence of sulfate corrosion on tunnel stability, the model parameters were determined in combination with the change rules of mechanical parameters of shotcrete obtained in the author’s experiment. The MIDAS GTSNX finite element software was used to analyze the effect of the hardening process of the shotcrete, chemical corrosion, and physical corrosion of sulfate on the displacement and stress of the surrounding rock of the tunnel. The results show that considering the hardening process of shotcrete, the growth rate of tunnel clearance displacement increases, and the stress increase slows in the early stage of shotcrete (The tunnel lining structure is applied, and the second step of excavation is carried out). With the increase of time or the construction steps, the stress of shotcrete increases significantly, and the clearance displacement growth rate significantly decreased. The influence of the chemical and physical corrosion of shotcrete on the stress and displacement of the surrounding rock of the tunnel is similar to considering the hardening process of shotcrete. indicating that sulfate corrosion has an inhibitory effect on the hardening process of shotcrete and increased construction risk.
Experimental study on the application of red mud to controlled low strength material made of excavated soil
Authors: Kong X H , Cui S , Chen L H , Wang X H 
Published: October 2021

Abstract
To improve the resource utilization of solid waste, excavation abandoned soil and red mud, a by-product of alumina industry, were introduced into the preparation of controlled low strength material (CLSM). By carrying out the flowability test, bleeding test and compressive strength test, the relationship between properties of CLSM mixture and the amount of red mud was analysed. The experiment results indicate that the flowability and bleeding rate of the mixture decrease with the increase of red mud content. When the red mud content is less than 20%, the mixture shows good flowability. The addition of red mud can accelerate the completion time of bleeding and play a positive role in the bleeding stability of the mixture. When the red mud content is 10%, the strength of the mixture reaches the maximum, while the strength of the mixture with other contents decreases with the increase of red mud content. For the CLSM made of excavated soil, red mud has a good application prospect in terms of bleeding stability and strength.
Effect of residual stress in longitudinal and transverse weld on global stability of box section steel column
Authors: Li L , Zheng F H , Zhang H D , Fu Y Q 
Published: October 2021

Abstract
In order to study the influence of welding residual stress on the global stability of box section steel column, the simulation of the side effects from the welding process of Q345 box section steel column by ABAQUS thermal-structure coupling analysis was conducted. A temperature-displacement explicit analysis step was established, and the residual stress caused by the temperature difference of the welding specimen was simulated by applying the body heat flux directly to the solid element within the same thickness range of the weld seam and defining the load amplitude; The calculated welding residual stress was taken as the initial defect of the structure and the global stable bearing capacity of the box section steel column was solved by the arc length method. Considering the influence of thickness and welding residual stress on the global stability of box section steel column, the calculation results of 12 finite element models were compared. The results show that under the same body heat flux, the residual stress of steel columns with different thicknesses during welding is different, and the maximum value can reach 791MPa; Under the condition of the same residual stress, the global stability bearing capacity of the box section steel column will also change irregularity with the change of thickness, and the global stability bearing capacity can be reduced by 3.07% compared with that no residual stress.
Raman Spectroscopy Studies of TRISO-Particle Fuel
Authors: Krajewska Zuzanna M , Gudowski W 
Published: October 2021

Abstract
Development of High Temperature Gas-cooled Reactors opens new horizons for nuclear power in Poland. Good understanding of the failure-free performance of Tri-structural ISOtropic (TRISO)-particle fuel is a key for the safe and efficient operation of those reactors. It is also essential to avoid potential errors in TRISO fuel production for the HTR program in Poland. In a longer perspective to ensure the highest possible quality of the TRISO fuel fabrication and storage before loading into the reactor core, it is necessary to control the quality of the TRISO-particle fuel in order to understand the aging of fresh fuel. Nevertheless, such a solution requires to determine whether the passage of time affects the occurrence of changes in TRISO fuel layer’s structure and at the same time whether it contributes to increasing the probability of damage to the examined fuel material. For this purpose, it is planned to perform an experiment on different types of TRISO fuel, produced in different periods of time. The comparative analysis will be based mainly on the experimental method of Raman spectroscopy.
Corrosion Phenomena of High Temperature Alloys by Helium Impurities in the Primary Coolant of HTGR
Authors: Wang Q , Zheng W , Yin H , Li S , He X , Ma T 
Published: October 2021

Abstract
The primary coolant circuit of the high temperature gas-cooled reactor (HTGR) contains trace impurities. A nickel base alloy would corrode when exposed to an atmosphere at a high temperature and for a long time. The protective oxide scale formed by chromium is an important factor to prevent severe corrosion of high temperature alloys. Corrosion tests were conducted on Inconel 617, Incoloy 800H, Hastelloy X, and T-22, which are commonly used in the steam generator of HTGR. The alloys were exposed to helium with trace impurities for 48 hours at 950°C. The corrosion results were analyzed by weighing, scanning electron microscopy (SEM) and electron probe microanalyzer (EPMA). All the four alloys formed oxide scales in this atmosphere, but they differ in the capacity to resist corrosion. Therefore, the carbon transfer phenomenon observed in this experiment varies for the different alloys. In addition, for Cr in Inconel617, the expected depletion phenomenon near the corrosion layer occurred, which is consistent with the results from theoretical analysis.
Accurate Nodal Diffusion Modelling on the High Temperature Test Reactor (HTTR)
Authors: Rizki M. , Oktavian  , Seker Volkan , Kochunas Brendan , Xu Yunlin 
Published: October 2021

Abstract
The High Temperature Test Reactor is a 30-MWth helium-cooled, graphite-moderated, prismatic-type gas reactor developed by the Japan Atomic Energy Agency (JAEA). The hexagonal shape of fuel blocks in the HTTR core combined with complex inner structures containing TRISO particles results in the double-heterogeneity effect that increases the simulation challenge of the reactor. This research has a goal to accurately model the HTTR fuel blocks employing the standard two-step procedure of a reactor analysis: employ a lattice physics calculation to generate homogeneous cross sections and use them in a nodal diffusion calculation. The implementation of the diffusion approximation results in a faster calculation with acceptable accuracy compared to the high-resolution lattice calculation. An advanced method called Triangular Polynomial Expansion Nodal (TriPEN) method was used in this work for the nodal diffusion calculation to accurately model the flux discontinuity effect between blocks by generating discontinuity factors in each surface and corner point. To do this, the heterogeneous solutions obtained from the lattice physics calculation, which is done by Serpent Monte Carlo in this case, are utilized by TriPEN to generate the discontinuity factors. Due to its capability to simulate any reactor geometry with a high-resolution, the results generated from Serpent calculation were also used as the reference cases for this work. In this work, the TriPEN method is implemented in the PARCS core neutronic module inside AGREE, a U.S. N.R.C. Multiphysics code system for the High Temperature Reactor (HTR). Test cases conducted for this method involved the original design of the HTTR. The 4-hex model built consisted of the central control-rod block of HTTR together with 6 of the half-fuel-blocks surround it. The differences in material composition in each assembly block in HTTR resulted in flux discontinuity effects on the assembly block interfaces. To correct this discrepancy, discontinuity factors were applied in order to make the homogenous solutions from the nodal calculation agree with the heterogeneous solutions from the lattice physics calculation. Applying this procedure to the HTTR nodal models, TriPEN is able to produce exact results in the eigenvalue compared to Serpent calculation, the rod worth calculated perfectly matched the reference, and the flux and power distribution only has negligible discrepancies.
Performance Improvement for Multi-recycling HTGR Incorporated with MA burning
Authors: Fukaya Y , Goto M , Yan X L 
Published: October 2021

Abstract
Multi-recycling HTGR has been investigated by JAEA in order to reduce the environmental burden and non-proliferation of Pu. In the previous study, it is found that all actinoids except neptunium, which is not problematic from the viewpoint of toxicity and proliferation, can be recycled. However, the cycle length is slightly decreased compared with uranium fueled core due to the cumulated fertile TRU in the fuel composition. In the present study, Pu recycling HTGR is designed to incorporate with MA burning. As a result, the cycle length is increased by approximately 15% compared with TRU multi-recycling core, and if the MA burner can be achieved by IFR, the cost is decreased by 0.14 yen/kWh.
Optimization of PeLUIt-150 Conceptual Design
Authors: Setiadipura T , Luthfi W , Bakhri S , Suwoto  , Zuhair  , Li Z , Sun Y 
Published: October 2021

Abstract
A 150MWt pebble bed high temperature reactor, called PeLUIt-150, is proposed as a solution for distributed energy demand including the electricity and various co-generation potentials. In current study an optimization of the design is performed. The optimization includes its optimum power density to have a compact core design including the height-to-diameter (H/d) ratio. As several computer codes is used in this study, PEBBED-THERMIX codes, comparison of results from different code is also discussed. Constrain of the design at current stage are the maximum fuel temperature under depressurized loss of forced cooling (DLOFC) accident which represent the passive performance of the core, and discharge burnup which represent the fuel utilization performance of the core. Current study achieves an optimized design with core diameter and height of 260 cm and 601.11cm, a total active core volume of 31.9 m3. The average power density is 4.7W/c m3 with discharge burnup of 80.82MWd/Kg and the maximum fuel temperature after DLOFC is 1619.9°C.
Impact of Different Nuclear Data Library on Control Rod Reactivity Worth Calculation of Small Pebble Bed Reactor
Authors: Suwoto  , Adrial H , Setiadipura T , Zuhair  , Bakhri S 
Published: October 2021

Abstract
One of the main critical issues on a nuclear reactor is safety and control system. The control rod worth plays an important role in the safety and control of nuclear reactors. The control rods worth calculation is used to specify the safety margin of the reactor. The main objective of this work is to investigate impact of different nuclear data libraries on calculating the control rod reactivity worth on small pebble bed reactor. Calculation of the control rod reactivity worth in small high temperature gas cooled reactor has been conducted using the Monte Carlo N-Particle 6 (MCNP6) code coupled with a different nuclear data library. Famous evaluated nuclear data libraries such as JENDL-40u, ENDF/B-VII.1 and JEFF-3.2 continuous cross section-energy data libraries were used. The overall calculation results of integral control rod worth show that the ENDF/B-VII.1, JENDL-40u and JEFF-3.2 files give values of - 17.814%☐k/k, -18.0204 %☐k/k and -18.0267%☐k/k, respectively. Calculations using ENDF/B-VII.1 give a slightly lower value than the others, while the JENDL-4.0u file gives results that are close to JEFF-3.2 file. The different nuclear data libraries have a relatively small impact on the control rod worth of small pebble bed reactor. Accurate prediction by simulation of control rod worth is very important for the safety operation of all reactor types, especially for new reactor designs.
Influence of Coiling Direction of Helical Tube Bundles on the Thermal-Hydraulics of the HTGR Steam Generator
Authors: Gao Weikai , Xie Xiaoyang , Li Xiaowei , Wu Xinxin 
Published: October 2021

Abstract
Helical tube bundles were usually adopted in the steam generators (SGs) or intermediate heat exchangers (IHXs) of high temperature gas-cooled reactors (HTGRs). Heat transfer tubes in neighboring tube layers can be coiled in the same direction or in the opposite direction. The coiling direction has influences on the thermal-hydraulic performances of the SGs or IHXs. The cross flow convection over helical tube bundles with neighboring tube layers having the same coiled direction and opposite coiled direction were numerically investigated. Reynolds stress model with standard wall functions was used for the turbulence modeling. For a helical tube bundle with neighboring layers coiled in the same direction (parallel tube layers), the tangential velocity along the coiled circumferential direction could be observed obviously. For a helical tube bundle with neighboring layers coiled in the opposite direction (crossed tube layers), there is no average tangential velocity of the whole flow filed. And the streamlines of the fluid are very complex. The flow resistances and heat transfer coefficients over helical tube bundle with parallel tube layers and crossed tube layers were compared. Although the heat transfer over helical tube bundles with crossed tube layers was 9.39% smaller than that with parallel tube layers, the pressure drop over tube bundle with crossed tube layers was much smaller compared with those with parallel tube layers.
Simulation System for PeLUIt 150 MW Nuclear Reactor by using vPower
Authors: Yunus M , Budiman A A , Zhe S , Kiswanta  , Chunlin W , Subekti M , Bakhri S , Jun S 
Published: October 2021

Abstract
In developing the PeLUIt 150 MW nuclear power plant based on the High Temperature Gas-cooled Reactor (HTGR) technology, with the helium-coolant and output thermal power of 150 MW, the PeLUIt simulator is also developed for training the operators and educating other technical personnel. Referred to the balance of plant (BOP) design of the PeLUIt, the simulator utilized the vPower simulation platform to simulate the secondary loop for power generation with a water-steam Rankine cycle. The paper focuses on developing the secondary loop’s main components: steam generator, steam turbine, condenser, deaerator, and feedwater pump. The reactor module in the primary loop is simplified as a heat source with 150 MW output. The steam generator that connects the primary and secondary loops is modeled with the heat exchanger module by transferring heat from helium to water/steam. Meanwhile, pressure and flow parameters can also be simulated for both helium and water/steam flows in steady-state and transient operating conditions. The steady-state simulation results are almost the same as the design data. The differences in the main steam temperature, feedwater pressure, and feedwater temperature, are 0.03%, 0.53%, and 0.02%, respectively. Meanwhile, the transient condition carried out in the loss of coolant accident showed a decrease in flowrate of 43.31 kg/s and an increase in temperature of feedwater and main-steam of 52.32 and 15.38 °C, respectively. In addition, there was a pressure drop of around 10.37 (feedwater) and 10.16 MPa (main-steam).
Modelling of FPGA-based Reactor Protection Systems of an Experimental Power Reactor
Authors: Suryono T J , Sudarno  , Santoso S , Maerani R 
Published: October 2021

Abstract
The reactor protection system of nuclear power plants including an experimental power reactor which will be built by Indonesia is a safety system that actuates the control rods to be inserted in the reactor core to absorb the neutron to stop the fission reaction and then shut down the reactor (reactor trip). The reactor protection system (RPS) is actuated when the level of signals from the sensors of important components in the reactors deviates from the setpoint determined in the bi-stable processor of the RPS. RPS for the experimental power reactor has 3 redundant channels for reliability and to minimize fake signals from the sensors due to electrical noise. It can be done by selecting the channels in local coincidence logic in the RPS by voting 2 of 3 channels which are eligible to generate actuation signals to trip the reactor. Recently, the RPSs are based on the programmable logic controller (PLC). However, now the trend changes to FPGA-based RPS because of its simplicity and reliability. This paper investigates the model of the FPGA-based RPS for an experimental power reactor and the functionality of each component of the model. The results show that the model can represent the functionality of RPS for the experimental power reactor.
Effect of mixing temperature in the development of green polypropylene – coal bottom ash composite slab
Authors: Mohd Yapandi Md Fauzan Kamal , Zainal Mohamad Fetri , Yusop Hanafi , Latif Famiza , Bonnia Noor Najmi , Jalil Mohammad Noor , Sukhairul Zaman Nur Zaqira Izzati 
Published: October 2021

Abstract
Coal bottom ash (CBA) is a residue produced from the burning of pulverized coal for electricity generation. The high porosity and low abrasion resistance of CBA hindered its commercialization; thus tonnes of CBA were discharged in landfills and surface impoundments. Considering the adverse social and environmental issues associated with disposal management, it is imperative to optimize the utilization of CBA. About 30% of CBA were homogeneously blended with Polypropylene (PP) to produce a “green” PP-CBA composite slab. The influences of mixing temperatures on the physical, chemical and mechanical properties of the fabricated slabs were examined in the study. FESEM micrographs illustrated a smoother surface with a low density of voids in composite systems mixed at low temperatures (190°C). Moisture content was retained in the PP-CBA matrix and imparted supplementary strength to the composite. The relatively amorphous state of the composite allowed for easier dispersion of molecules under applied stress. From the tests, PP-CBA composite slabs mixed at 190°C exhibited the largest drop impact energy and ideal physical and structural properties.
Assessing biofouling in Ocean Thermal Energy Conversion (OTEC) power plant – A review
Authors: Zainal Abidin Mohd Zaki , Muhd Rodhi Miradatul Najwa , Hamzah Fazlena , Ghazali Nurul Aimi 
Published: October 2021

Abstract
Ocean Thermal Energy Conversion (OTEC) harnesses thermal energy stored at different seawater depths via power generation from a thermodynamic closed-loop cyclical system. Apart from its consistent energy generation, it could be diversified into other side industries, making OTEC an attractive and sustainable source of renewable energy. However, the process that utilises seawater as its main fluid is exposed to biofouling deposition due to unwanted growth and accumulation of biological elements on any contact surfaces, potentially affecting its efficiency and damaging equipment in the process. Considering that biofouling is an inevitable condition that may not be eliminated, a comprehensive study for assessing potential biofouling growth and deposition mechanism is a crucial step for strategizing effective biofouling management in a commercial and large-scale OTEC power plant facility. This review paper focuses on evaluating suitable biofouling assessment techniques specifically for a large-scale OTEC power plant facility. This is achieved by evaluating previous and proposed biofouling assessment techniques relevant to OTEC systems by focusing on their implementation under a realistic OTEC setup. The initial study indicated that the potential of biofouling deposition may be unavoidable in some sections in all OTEC models, despite biofouling-free design consideration. Previous OTEC biofouling studies were evaluated with reported physical and biological assessment approaches indicated the need to further improve these techniques especially in continuous and non-destructive methods. Therefore, several biofouling monitoring systems reported from other water treatment industries were considered for the OTEC systems, with findings indicated the importance of considering important OTEC operational parameters for feasible and robust biofouling monitoring systems. Two major parameters which are seawater intake flow rate and temperature variation at different seawater intake levels were evaluated under OTEC operational evaluation by considering examples of practices conducted in cooling water systems in the power plant industry. A realistic biofouling monitoring setup for mimicking continuous changes in biofouling deposition is required, in this case by side-connecting an operated OTEC power plant facility with a pilot plant setup or a side sampler. This step allows the application of proposed biofouling monitoring techniques under a realistic and uninterrupted biofouling deposition setup.