Control rods

Xem 1-20 trên 33 kết quả Control rods
  • This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor. To investigate the drop performance, a real-sized control rod assembly that was recently modified based on the drop analysis results was newly fabricated, and several free drop tests under different flow rate conditions were carried out.

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  • The main purpose of this work is to use the MTR_PC package to evaluate the effect of the partially insertion of the control rod on the neutronic parameters at the operating core of the Tehran Research Reactor. The simulation results show that by increasing the insertion of control rods (bank) in the core, the absolute values of power peaking factor, reactivity coefficients and effective delayed neutron fraction increased and only prompt neutron life time decreased.

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  • In this paper, three-dimensional neutronic calculations were performed in order to calculate the dependency of CRW on the temperature of fuel and moderator and the moderator void. Calculations were performed using the known MTR_PC computer codes in the core configuration 61 of TRR. The dependency of CRW on the fuel temperature in the range of 20e340 C and the moderator temperature of each control rods were studied.

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  • The control rod assembly controls reactor power by adjusting its position during normal operation and shuts down chain reactions by its free drop under scram conditions. Therefore, the drop performance of the control rod assembly is important for the safety of a nuclear reactor. In this study, the drop performance of the conceptually designed control rod assembly for the prototype generation IV sodium-cooled fast reactor that is being developed at the Korea Atomic Energy Research Institute as a next-generation nuclear reactor was experimentally investigated.

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  • This study simulated a control rod assembly (CRA), which is a part of reactor shutdown systems, in immersed and fluid flow conditions. The CRA was inserted into the reactor core within a predetermined time limit under normal and abnormal operating conditions, and the CRA (which consists of complex geometric shapes) drop behavior is numerically modeled for simulation.

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  • The present study aims to assess the excess induced reactivity in a Miniature Neutron Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario. The BDBA scenario as defined in the Safety Analysis Report (SAR) of the reactor involves sticking of the control rod and filling of the inner and outer irradiation sites with water. At the end of the MNSR core life, 10.

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  • Flaws at dissimilar metal welds (DMWs), such as reactor coolant systems components, Control Rod Drive Mechanism (CRDM), Bottom Mounted Instrumentation (BMI) etc., in nuclear power plants have been found. Notably, primary water stress corrosion cracking (PWSCC) in the DMWs could cause significant reliability problems at nuclear power plants. Therefore, phased array ultrasound is widely used for inspecting surface break cracks and stress corrosion cracks in DMWs.

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  • The objectives of research contents of the thesis: (i) to synthesize and investigate the optical properties of gold nanostructures spherical, rod and core/shell SiO2/Au shape with controlled sizes; (ii) to try application of synthesized gold nanostructures in imaging and in photothermal.

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  • To assess the relationship between mechanical wear and the failure of the internal lengthening mechanism in retrieved MAGnetic Expansion Control (MAGEC) growing rods. Methods: This study included 34 MAGEC rods retrieved from 20 patients. The state of the internal mechanism and mechanical wear were assessed in all the rods using plain radiographs and visual inspection.

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  • In today’s practical and cost-conscious world, sheet-metal parts have already replaced many expensive cast, forged, and machined products. The reason is obviously the relative cheapness of stamped, or otherwise mass-produced parts, as well as greater control of their technical and aesthetic parameters. That the world slowly turned away from heavy, ornate, and complicated shapes, and replaced them with functional, simple, and logical forms only enhanced this tendency. Remember old bathtubs? They used to be cast and had ornamental legs.

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  • In BWR’s steam bubbles have a negative steam bubbles have a negative reactivity feedback, if the steam fraction reactivity feedback, if the steam fraction increases in the core the reactor power increases in the core the reactor power decreases

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  • Dynamics of a Two-Rod Element Choice of Independent Variables and Coordinate Transformations 18.5 Tendon Forces 18.6 Conclusion Appendix 18.A Proof of Theorem 18.1 Appendix 18.B Algebraic Inversion of the Q Matrix Appendix 18.C General Case for (n, m) = (i, 1) Appendix 18.D Example Case (n,m) = (3,1) Appendix 18.E Nodal Forces

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  • In rod phototransduction, cyclic GMP synthesis by mem-brane bound guanylate cyclase ROS-GC1 is under Ca 2+ -dependent negative feedback control mediated by guanylate cyclase-activating proteins, GCAP-1 and GCAP-2. The cellular concentration of GCAP-1 and GCAP-2 approxi-mately sums to the cellular concentration of a functional ROS-GC1 dimer. Both GCAPs increase the catalytic effi-ciency (kcat /Km) of ROS-GC1. However, the presence of a myristoyl group in GCAP-1 has a strong impact on the regulation of ROS-GC1, this is in contrast to GCAP-2....

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  • In this study, the operation and response capability of safety system in nuclear reactor WWER-1000 was analyzed during the accidents that involved the failure of main circulation pump or feed water pumps. The nuclear reactor WWER-1000 simulator developed by IAEA showed that safety systems such as the EP, the PP and the AUU are capable of controlling the reactor power by adjusting the control rods during the accidents.

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  • This study constitutes the first isolation and characterization of local B. thuringiensis isolates in Syria. Some of these isolates exhibit toxic potential, therefore could be adopted for future applications to control some important insect pests.

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  • The comprehensive diagnosis ontology database, including the knowledge domains of fault, collection and structure, is established. And the relationships among the ontology are described.

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  • This research also introduces a supplementary reactivity control mechanism using stainless steel as mechanical shim (MS) rod to obtain the criticality during normal operation. A further analysis is performed to investigate the local power peaking of the CSBA-loaded FA at MS-rodded condition. Moreover, a simple B4C-based control rod arrangement is proposed to assure a sufficient shutdown margin even at the cold-zero-power condition.

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  • This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, q) and 3-D (r, q, z), using WIMS-D/4 and PRIDE codes.

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  • The purpose of this study is to investigate whether an SMR would have enough control rod worth to compensate for large reactivity feedback. The investigation begins with classification of reactivity and completes an analysis of the reactivity balance in each reactor state for the SMR model.

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  • Mechanical shim is an advanced technology for reactor power and axial offset control with control rod assemblies. To address the adverse accuracy impact on the ex-core power range neutron flux measurements-based axial offset control resulting from the variable positions of control rod assemblies, the lead-lag-compensated in-core self-powered vanadium detector signals are utilized.

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