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At least 1,261 records · Page 70
All sourcesNASA NTRSDOE OSTI
DOE OSTI2016

General description of HTR-PM emergency power system - 18415

The paper will describe the design concept of the emergency power system utilized in the high temperature gas cooled reactor project (HTR-PM) which is currently under construction in Shandong, China. As a class 1E system which is related to the safety feature of the reactor, emergency power system is responsible for providing multiple reliable power sources for nuclear safety class loads. Therefore, the structure, power source deployment, operation, maintenance and alignment of the system should meet several standards and regulations. The paper will give a detailed description about the designing process of the system which include structure design, determination of primary device parameters, and some calculation results of device capacity such as emergency diesel engine, UPS et al. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Design and Preparation of SiC-ZrC Composite Coating Layers by FB-CVD Used in TRISO Coated Fuel Particles - 18417

Tri-structural-isotropic (TRISO) particle has been successful in high temperature gas cooled reactor (HTGR), but an improved design is required for future development. In this paper, two alternative designs of TRISO particle are proposed by introducing ZrC to the coating layers. One design is to add an individual ZrC layer between the inner PyC layer and the SiC layer. Another design is to construct a periodic coating layer with the repeated sequence of SiC/SiC-ZrC by doping pulsed ZrCl{sub 4} at proper time intervals during the SiC preparation process. The designed coating layers were successfully prepared on the ZrO{sub 2}/buffer/IPyC particles by the fluidized bed chemical vapor deposition (FB-CVD) method. Microstructures and characterizations of the composite coating layers were given based on XRD, SEM, EDX and Raman scattering analysis. By controlling the pulse parameter, the grain size of SiC is significantly decreased which means doping ZrCl{sub 4} can interrupt normal growth of SiC crystals. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

The process heat applications of HTGR in petroleum refining industry: adaptability and economy - 18425

High Temperature Gas Cooled Reactor (HTGR) is considered as a kind of potential heat producer for industry. Since the industrial heat utilization takes 60% of heat supply in China, the process heat of HTGR is more suitable for industrial manufacturing as high temperature heat source. In this article, the adaptabilities of HTGR for heat supply to petroleum refining industry are analyzed and it is found that the joint of process heat of HTGR and chemical industry is most predictable in the near future. For case study, technical and economic analysis of process heat-supply proposal in a typical refinery in China is finished and it is shown that though there is some technical and conceptual challenge, the application of process heat of HTGR in petroleum refining industry is feasible and competitive in economics. (authors)

02 PETROLEUM↗
DOE OSTI2016

The electric current effect on electrochemical deconsolidation of spherical fuel elements - 18447

For High-Temperature Gas-cooled Reactor in China, fuel particles are bonded into spherical fuel elements by a carbonaceous matrix. In conjunction with the development of a system to determine fuel failure fractions through {gamma}-analysis of individual and undamaged fuel particles, an automated electrochemical deconsolidation apparatus was developed in this study to separate the particles from the carbonaceous matrix by disintegrating the matrix into fine graphite powder, based on the anodic oxidation of graphite in an electrolyte containing nitric acid. A series of tests were conducted under a range of deconsolidation conditions to develop procedures and refine the equipment. The easy-handle un-irradiated spherical fuel elements were used as samples for initial tests. It is found that the morphology, size, and element content of deconsolidated graphite matrix and free particles were notably affected by electric current intensity. During the electrolysis, the nitric acid electrolyte gradually infiltrated into the micropores of graphite matrix, and the electrochemical reaction would take place around micropore structure as well as matrix surface. With much higher surface reaction capability due to the large specific area of micropore structure, the expansion stress originated from inner surface of micropores widened the c-spacing of the layer lattice of carbonaceous matrix, which was thought to be one of the main driving force of deconsolidation. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Summary and experience feedback on the restart and power operation after a long term shutdown of HTR-10 - 18460

After a long term shutdown, 10 MW high temperature gas-cooled reactor (HTR-10) has been restarted in 2014. The main content of this process has been summarized and presented. The preparation in the reactor shutdown stage, the characteristic tests after the restart, and the engineering practice and experience during the power operation of HTR-10, have been introduced in details. The experience feedback on the restart process and power operation stage of HTR-10 have been proposed, including the equipment maintenance, technical transformation, routine test and inspection, modification of operational limits and conditions, and personnel training, etc. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Development of safety requirements for HTGRs design - 18467

The safety requirements for the design of High Temperature Gas-cooled Reactors (HTGRs), which is analogous to the IAEA specific safety requirements (SSR) for Light Water Reactor (LWR) design (IAEA SSR-2/1), has been developed by the research committee established in the Atomic Energy Society of Japan so as to incorporate the HTGR safety features demonstrated by High Temperature Engineering Test Reactor (HTTR), lessons learned from the accident of Fukushima Daiichi Nuclear Power Station and requirements for the coupling of the hydrogen production plants with nuclear plant. The safety design approach was determined to establish a high level of safety design standards by utilizing inherent safety features of HTGRs. The safety requirements is then developed using the objectives provisions tree methodology based on the safety design approach. The requirements for a structural integrity of fuel during accident conditions, for a confinement structure instead of a leak-tight pressure resistance containment vessel, for a passive residual heat removal from outside of reactor pressure vessel, etc., which are significantly different from those of LWR, are stated in the developed safety requirements. This paper describes overview of the proposed HTGR specific safety requirements. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Thermal hydraulic issues of HTGR helical tube once through steam generator: methods and applications - 18478

High Temperature Gas-cooled Reactor (HTGR) usually uses helical tube once through steam generators (OTSG) for steam generation. The most concerned thermal hydraulic issues of HTGR helical tube OTSG are two phase flow instability and temperature non-uniformity. One dimensional transient code and two dimensional code are developed to investigate these two issues. The codes are briefly introduced, then the results are briefly presented and discussed. The main conclusions are that there does not appear two phase instability for all the working conditions for the steam generator of HTR-PM. Tube plugging can introduce temperature non-uniformity in the tube bundle. The temperature non-uniformity can be evened by changing the flow rate distribution through adjusting the throttle orifice at the inlet. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Surface-modified microchannel-type process heat exchanger (PHE) for hydrogen production using sulfur-iodine cycle - 18481

For massive production of hydrogen using a very high temperature gas-cooled reactor (VHTR) system, a small-scale process heat exchanger (PHE) for feasibility testing of a sulfur-iodine (S-I) cycle is designed at KAERI. Printed circuit type heat exchanger (PCHE), which is suitable for a helium/decomposed sulfuric acid (SO{sub 3}/SO{sub 2}) heat transfer system, is employed with surface modification to protect the substrate alloy from the corrosive sulfuric acid environment. Experiments on diffusion bonding, which is a key technology in compact-type heat exchangers, are conducted to achieve considerable strength and ductility at both room and high temperature. Metallographic examination reveals the migrated grain boundary across the interface. Tensile ductility over 35 % is achieved and dimples are observed on the fracture surface in all testing temperatures. For surface modification, β-SiC having high corrosion resistance is deposited on the surface of the microchannels using electron beam physical vapor deposition (EB-PVD) followed by ion-beam irradiation to enhance the adherence at the interface of β-SiC/alloy. Through corrosion testing in aqueous sulfuric acid (60 vol.%), the weight loss of the surface-modified specimens is decreased by one order of magnitude, implying the relevance of coating for this application. (authors)

08 HYDROGEN↗
DOE OSTI2016

Development of a core coolant flow distribution calculation code for HTGRs - 18484

In order to ensure the thermal integrity of fuel in high temperature gas-cooled reactors (HTGRs), it is necessary that the maximum fuel temperature in the normal operation is to be lower than the thermal design target. In the core thermal-hydraulic design of block-type HTGRs, the maximum fuel temperature should be evaluated considering data such as thermal power, core geometry, power and neutron fluence distributions, and core coolant flow distribution. The core coolant flow distribution calculation code used in the design stage of High Temperature engineering Test Reactor (HTTR) presupposes to run on UNIX systems, and its operation and execution procedure are complicated and not user-friendly. Therefore, a new core coolant flow distribution calculation code with a user-friendly system such as simple and easy operations and execution procedures has been developed. In this paper, the outline of the new code is described and the simulation result of an out-of-pile test with one fuel column are shown as the first step of the code validation. The simulation results provide good agreement with the test one. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Study on balance of axial force in helium circulator for HTR-PM - 18490

The helium circulator is one of the key equipment in the first loop of the High Temperature gas-cooled Reactor Pebble bed Module (HTR-PM). The active magnetic bearings are employed in the helium circulator, so that the inlet ring sealing clearance is about 5 to 10 times larger than that if the mechanical bearings are employed. Bigger clearance results in bigger leakage flow and bigger axial force. A new design of balance holes was proposed to reduce the axial aerodynamic force and the design principle was analyzed. To investigate the axial aerodynamic force due to leakage flow, numerical simulation of fluid dynamic was conducted in the impeller with two kinds of inlet ring sealing clearance and four types of balance holes, respectively. The calculation results shows that the balance holes with diameter 12 mm have high performance and that the designed balance holes reduce effectively about 78% of the axial aerodynamic force. The axial force was obtained from the measured real-time electric current of the axial active magnetic bearings in one helium circulator prototype. The comparison of experimental data with the CFD analysis results showed that the new design of balance holes was successful. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Development of random geometry capability in RMC code for explicit analysis of polytype particle/pebble - 18493

Monte Carlo method plays an important role in accurate simulation of High Temperature Gas-Cooled Reactors (HTR) and molten salt reactors, owing to its advantages of the flexible geometry modeling and the use of continuous-energy nuclear cross sections. For the innovative design of pebble bed, prism HTRs and molten salt reactors, there may be more than one kind of particles or pebbles in the system, such as the burnable poison particles, graphite pebbles or fuel pebbles with different enrichments. Different treatments have been used to deal with the double-heterogeneous geometry of these reactors. In some researches, the particle distributions in stochastic media are assumed the regular lattice, while in the others, the explicit packing methods such as Random Sequential Addition (RSA) and Discrete Element Method (DEM) are used, by generating the random coordinates of the particles/pebbles. However, traditional geometry with repeated structure has difficulties in explicit modeling polytype particle/pebble, due to the arbitrary packing fractions of different kinds of particles or pebbles. Although, packing methods such as Random Sequential Addition (RSA) and Discrete Element Method (DEM) could solve the polytype particle/pebble problems to some extent, but these methods are troublesome in geometry modeling and time consuming. In this paper, a new Random Universe Geometry method was developed and implemented in Monte Carlo code RMC, for explicit analysis of polytype particle/pebble in double heterogeneous geometry systems, such as HTRs and molten salt reactors. This method was applied to constructed mixed particles/pebbles problems and also simplified HTR-10 full core problem to test the feasibility, and the results show that the random geometry modeling can provide explicit packing fraction of different kinds of particles or pebbles. The results are also compared with that calculated by RSA method and regular structure, and agree quite well. This work would provide an effective tool for the innovative design of pebble bed, prism HTRs and molten salt reactors with polytype particles or pebbles using Monte Carlo method. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Graphite Dust Deposition on HTGR Steam Generator: Effect of Particle-wall Impact - 18520

Generated by abrasion of fuel spheres, graphite dust is an important issue for the operation and maintenance of high-temperature gas-cooled reactor (HTGR), since the transport of fission product is closely coupled with graphite dusts. AVR experiments on dust specific radioactivity indicate that graphite dust deposition on steam generator (SG) should be of special interest. Most previous simulations on graphite dust deposition assume a hit-and-stick nature for particles, which may overestimate the deposition rate. In this work we uses a critical velocity model to account for particle-wall interaction. Combined with computational fluid dynamics simulation and discrete phase method, the deposition of graphite dust in the upper 22 layers of SG tubes was studied with particle-wall interaction considered. The result shows that the deposition rate is highly overestimated if hit-and-stick is assumed. For particles larger than 5 {mu}m, the difference can be as large as 3 times. Particle deposition rate reaches maximum at about 3 {mu}m. As for the spatial distribution, few particles deposit on the first layer of tubes due to relative low Stokes number while more depositions occur after entering bundle zone, which indicates that the unsteady wake among tubes could be a major mechanism for the deposition. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Performance tests of helium circulator under abnormal cooling conditions - 18523

Helium circulator is one of the key equipment of High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM) and the unique rotating equipment of primary loop. It transports heat generated by fission reactions from reactor core to steam generator by forcing helium circulating in primary loop. As the study on the characteristics of helium circulator in HTGR was limited and the advanced designs integrated with many new technologies, a prototype of helium circulator was manufactured. It was supported by Active Magnetic Bearings (AMBs), and was assembled in a pressure vessel. The prototype was tested in Engineering Test Facility - Helium Circulator (ETF-HC), which is a full scale, rated flow rate and power, engineering test loop. Although performance tests under normal operation condition were successfully fulfilled, the complete features and performance still need further verification, especially for abnormal cooling conditions. Thus performance tests under abnormal cooling operation conditions were carried out. Tests such as temporary coolant loss of motor and AMBs cooler and abnormal high-temperature cooling water condition were fulfilled. All performance tests results showed that helium circulator met the entire requirement of HTR-PM plant under abnormal cooling conditions and validated its safety and reliability. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Effect of double heterogeneity treatment on neutronics modeling of HTGR unit cell - 18524

The High Temperature Gas-cooled Reactor (HTGR) utilizes unique coated fuel particle design, which is embedded within a graphite matrix and shaped into spherical or hexagonal fuel element. The feature of the inherent double heterogeneity in the HTGR fuel element therefore raises difficulties in modeling and requires special simulation strategies to address its impact on the self-shielding calculation. In this study, neutronics calculations with various levels of heterogeneity processing were performed for both spherical and hexagonal HTGR fuel elements. The results indicate that ignoring either level of double heterogeneity can lead to significant underestimation of self-shielding effect and consequently yield as much as 8% deviation in the prediction of the multiplication factor. Fission and capture rates were compared for the spherical HTGR fuel model and over 30% deviation was found in the resonance energy range if homogenized model used. Further investigation on the neutron spectrum demonstrated similar tendency for both types of fuel elements when applying the simplified self-shielding models, that is, {approx}20% underestimation of neutron flux in 6.5-6.75 eV energy interval was observed due to the incomplete evaluation of the cross section resonance self-shielding effect. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

The development of 3D physical program with integrated control rod calculation for HTR - 18525

The accurate calculation of the control rod worth in pebble bed high temperature gas cooled reactor(HTR) requires special treatment, because the control rod system of HTR is located outside the active zone. The current version VSOP did not calculate the control rod value directly, but use a compromise method called the Equivalent Boron Concentration (EBC). To obtain the value of the control rod with higher precision directly, this paper embedded the discontinuity factor (DF) corrected diffusion calculation into the original procedure of the VSOP. The computational procedure to obtain the DF on the side of the absorber region was optimized. While an appropriate coupling method has been developed to take into account the neutron leakage feedback, data transform and so on. The new program can achieve accurate control rod calculation and more realistic 3D power distribution during the physical calculation. The numerical results demonstrated the correctness of the new program preliminarily. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

React-compact: a computer code for modeling graphite corrosion and fuel hydrolysis - 18526

REACT-COMPACT is used to estimate localized graphite corrosion, fuel compact corrosion, and fuel hydrolysis by water vapor for a unit cell geometry within a High Temperature Gas Cooled Reactor (HTGR) fuel block. REACT-COMPACT may also be used to model corrosion in regions with graphite only, including core support posts. REACT-COMPACT solves the species-conservation equation for water vapor in a porous carbon medium for cylindrical geometry. Boundary-layer mass transfer from a helium coolant is modeled at either the inner or outer radius. Within the porous carbon medium, both diffusive and convective transport mechanisms are modeled. The reaction of water vapor with carbonaceous materials is modeled according to a Langmuir-Hinshelwood mechanism. The fuel hydrolysis reaction rate is based on a semi-empirical model derived from experimental data. Model parameters, including densities, void fractions, burn off factors for the intrinsic reaction rates, and diffusivity of water vapor in porous carbon, are evaluated as functions of local burn off. The effects of void-fraction gradients on transport processes are also modeled. REACT-COMPACT also solves the mass conservation equations for reacting fuel and carbonaceous materials, which are coupled in a nonlinear manner to the water-vapor conservation equation because of burn off effects. For this reason, a numerical finite-difference solution is used. This paper describes the theoretical basis for REACT-COMPACT and results for sample problems under representative HTGR conditions. (author)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Endurance test of helium circulator for HTR-PM - 18531

High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM) will be built as the world's first pebble-bed type modular HTGR commercial demonstration plant according to Chinese National science and technology program. HTR-PM will be expected to begin generating electricity in the end of 2017 in Shidao bay of China. Helium circulator is one of critical component of HTR-PM, which circulates reactor coolant through the reactor core and steam generators. The helium circulator was designed to be a vertical layout and its rotor was supported by active magnet bearings (AMBs). The whole circulator including motor and cooler was sealed in a pressure vessel. Since it is a large mechanical and electrical equipment and the design is totally advanced integrated with many new technologies, experiment study of helium circulator would be significant for safe and reliable operation of HTR-PM plant in the future. For the lack of engineering experience of this equipment, it was necessary to manufacture a prototype for tests. Meanwhile, Engineering Test Facility- Helium Circulator. ETF-HC was built in Institute of Nuclear and New Energy Technology (INET) for the tests. The prototype is completely same as the real machine for the plant. After prototype fabrication, nitrogen test was firstly conducted in the factory by the manufacturer, designer and users. After successful factory test, the prototype was delivered to INET to be tested in ETF-HC. Although nitrogen simulation test had been completed successfully, helium endurance test has been continually carried out in ETF-HC for one and half years because of several sealing problems caused by helium. After solving all kinds of problem in the field, helium circulator run continuously 50 hours under rated condition. Furthermore, 50 service cycles test was conducted in ETF-HC. More than 500 operation hours was accumulated during endurance test. Throughout the final performance test, a conclusion can be made that the helium circulator performance met the design requirements and its feasibility, availability and reliability was verified. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2016

Modeling and analysis of an AMB system with flexible rotor in HTR-10GT - 18550

Active magnetic bearing (AMB) has been widely used in high-temperature gas-cooled reactor (HTR) for its specific properties: free of contact, absence of lubrication, capability of rotating at high speed. AMB system is inherently unstable since positive feedback exists in the open loop system and, thus, requires feedback control. From the control view of point, accurate system model is essential for designing of an effective controller especially when the flexible gyroscopic rotor is involved. In the paper, a flexible rotor and an open-loop AMB system model were established for the purpose of controller design. Dynamic characteristics of the undamped flexible rotor are analyzed including modal vibration analysis and undamped natural frequencies. Additionally, some characteristics of open-loop AMB system are investigated such as relationship between support stiffness and natural frequencies, and the system frequency response. The analysis results in this paper will provide valuable information for AMB system feedback controller design. (authors)

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗