The Shandong Shidao Bay 200 MW_e High-Temperature Gas-Cooled Reactor Pebble-Bed Module(HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation

In 2005, the US passed the Energy Policy Act of 2005 mandating the construction and operation of a high-temperature gas reactor （HTGR） by 2021. This law was passed after a multiyear study by national experts on what future nuclear technologies should be developed. As a result of the Act, the US Congress chose to develop the so-called Next-Generation Nuclear Plant, which was to be an HTGR designed to produce process heat for hydrogen production. Despite high hopes and expectations, the current status is that high temperature reactors have been relegated to completing research programs on advanced fuels, graphite and materials with no plans to build a demonstration plant as required by the US Con- gress in 2005. There are many reasons behind this diminution of HTGR development, including but not limited to insufficient government funding requirements for research, unrealistically high temperature requirements for the reactor, the delay in the need for a ＂hydrogen＂ economy, competition from light water small modular light water reactors, little utility interest in new technologies, very low natural gas prices in the US, and a challenging licensing process in the US for non-water reactors.

Adaptive output-feedback power-level control for modular high temperature gas-cooled reactors

Small modular reactors(SMRs) are beneficial in providing electricity power safely and viable for specific applications such as seawater desalination and heat production. Due to its inherent safety feature, the modular high temperature gas-cooled reactor(MHTGR) is considered as one of the best candidates for SMR-based nuclear power plants. Since its dynamics presents high nonlinearity and parameter uncertainty, it is necessary to develop adaptive power-level control, which is beneficial to safe, stable, and efficient operation of MHTGR and is easy to be implemented. In this paper, based on the physically-based control design approach, an adaptive outputfeedback power-level control is proposed for MHTGRs. This control can guarantee globally bounded closedloop stability and has a simple form. Numerical simulation results show the correctness of the theoretical analysis and satisfactory regulation performance of this control.

Oxidation behaviors of wrought nickel-based superalloys in various high temperature environments

Oxidation characteristics of Alloy 617 and Haynes 230 at 900 oC in simulated helium environment,hot steam environment containing H2 as well as in air and pure helium conditions were investigated.Compared to air condition,the oxidation rate of Alloy 617 was not significantly affected in helium and hot steam environments,while Haynes 230 showed lower oxidation rate in helium environment.On the other hand,the oxide morphology and structure of Alloy 617 were strongly affected by the environments,but those of Haynes 230 were less dependent on the environments.For Haynes 230,a Cr2O3 inner layer and a protective MnCr2O4 outer layer were formed in all environments,which contributed to the better oxidation resistance.As the mechanical properties,such as creep and tensile properties,were significantly affected by the oxidation behaviors,surface treatment methods to enhance oxidation resistance of these alloys should be developed.

HTR-PM汽轮机轴封蒸汽断供原因分析及解决方案

介绍了高温气冷堆示范工程(HTR-PM)汽轮机轴封系统,并且对轴封蒸汽断供的原因进行了分析,提出了可以采用蒸汽发生器及管道内余汽供轴封、辅助电锅炉至轴封供汽管道改造、高温空气供轴封这3种解决方案。对3种方案进行对比,分析其在成本、可靠性和运行限制方面的优缺点,结果表明3种方案均是可行的。研究结果为HTR-PM汽轮机轴封蒸汽断供问题的解决提供了参考。

荒漠植物花花柴HTR基因家族表达模式及其增强细菌抗逆性分析

【目的】荒漠植物花花柴具有耐盐碱、耐高温等优异的广谱抗逆性,是新疆珍贵的天然抗逆植物种质资源。挖掘花花柴耐极端温度和耐盐基因,系统分析其在高温、低温和高盐胁迫下表达模式以及抗逆性,对于利用该基因增强作物抗逆性、稳产性、丰产性,促进荒漠植物基因资源的发掘利用都具有重要意义。【方法】采用盆栽花花柴幼苗进行不同时长的高温(45℃)、低温(4℃)和高盐(400 mmol/L Na^(+))胁迫处理,采集幼苗的根、茎、叶组织,利用RT-PCR等技术克隆花花柴HTR基因家族(KcHTRs),分析KcHTRs基因表达情况,同时通过原核表达体系分析其抗逆性以及表达蛋白质的最佳诱导条件。【结果】(1)从荒漠植物花花柴高温转录组数据中筛选并克隆了KcHTR基因家族的7个成员,通过构建原核表达载体并诱导表达,明确其cDNA长度在708~789 bp之间,所表达的蛋白质分子量在27~29 kD之间;(2)发现在大肠杆菌BL21最适生长温度37℃下该家族蛋白的最佳诱导表达体系:OD600为0.8,IPTG诱导浓度为0.5 mmol/L,诱导时间为8~10 h;(3)通过对重组大肠杆菌的模拟高温、低温、盐胁迫处理,结果显示KcHTRs能够在一定程度上增强宿主对高温、低温和高盐的耐受性。【结论】KcHTRs具有优异的广谱抗逆性,主要具有耐极端温度的抗逆性,且能够积极响应花花柴植株应对逆境胁迫。

Numerical investigations of thermal mixing performance of a hot gas mixing structure in high-temperature gas-cooled reactor

A numerical simulation study was performed to clarify the thermal mixing characteristics of coolant in the core bottom structure of the high-temperature gas-cooled reactor(HTR). The flow field and temperature field in the hot gas chamber and the hot gas duct of the HTR were obtained based on the commercial computational fluid dynamics(CFD) program. The numerical simulation results showed that the helium flow with different temperatures in the hot gas mixing chamber and the hot gas duct mixed intensively, and the mixing rate of the temperature in the outlet of the hot gas duct reached 98 %. The results indicated many large-scale swirling flow structures and strong turbulence in the hot gas mixing chamber and the entrance of the hot gas duct, which were responsible for the excellent thermal mixing of the hot gas chamber and the hot gas duct. The calculated results showed that the temperature mixing rate of the hot gas chamber decreased only marginally with increasing Reynolds number.

Study on neutronics design of ordered-pebble-bed fluoride-salt- cooled high-temperature experimental reactor

This paper presents a neutronics design of a 10 MW ordered-pebble-bed fluoride-salt-cooled high-temperature experimental reactor. Through delicate layout, a core with ordered arranged pebble bed can be formed,which can keep core stability and meet the space requirements for thermal hydraulics and neutronics measurements.Overall, objectives of the core include inherent safety and sufficient excess reactivity providing 120 effective full power days for experiments. Considering the requirements above, the reactive control system is designed to consist of 16 control rods distributed in the graphite reflector. Combining the large control rods worth about 18000–20000 pcm, molten salt drain supplementary means(-6980 to -3651 pcm) and negative temperature coefficient(-6.32 to -3.80 pcm/K) feedback of the whole core, the reactor can realize sufficient shutdown margin and safety under steady state. Besides, some main physical properties, such as reactivity control, neutron spectrum and flux, power density distribution, and reactivity coefficient,have been calculated and analyzed in this study. In addition, some special problems in molten salt coolant are also considered, including ~6Li depletion and tritium production.

Design of the material performance test apparatus for high temperature gas-cooled reactor

Most materials can be easily corroded or ineffective in carbonaceous atmospheres at high temperatures in the reactor core of the high temperature gas-cooled reactor(HTGR).To solve the problem,a material performance test apparatus was built to provide reliable materials and technical support for relevant experiments of the HTGR.The apparatus uses a center high-purity graphite heater and surrounding thermal insulating layers made of carbon fiber felt to form a strong carbon reducing atmosphere inside the apparatus.Specially designed tungsten rhenium thermocouples which can endure high temperatures in carbonaceous atmospheres are used to control the temperature field.A typical experimental process was analyzed in the paper,which lasted 76 hours including seven stages.Experimental results showed the test apparatus could completely simulate the carbon reduction atmosphere and high temperature environment the same as that confronted in the real reactor and the performance of screened materials had been successfully tested and verified.Test temperature in the apparatus could be elevated up to 1600oC,which covered the whole temperature range of the normal operation and accident condition of HTGR and could fully meet the test requirements of materials used in the reactor.

Analysis on thermophoretic deposit of fine particle on water wall of 10 MW high temperature gas-cooled reactor

The water wall is an important part of the passive natural circulation residual heat removal system in a high temperature gas-cooled reactor. The maximum temperatures of the pressure shell and the water wall are calcu- lated using annular vertical closed cavity model. Fine particles can deposit on the water wall due to the thermophore- sis effect. This deposit can affect heat transfer. The thermophoretic deposit efficiency is calculated by using Batch and Shen’s formula fitted for both laminar flow and turbulent flow. The calculated results indicate that natural convection is turbulent in the closed cavity. The transient thermophoretic deposit efficiency rises with the increase of the pressure shell’s temperature. Its maximum value is 14%.

Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment

Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized water reactor(PWR), the methods and steps of PSA in FHR should be studied. The high-temperature gascooled reactor(HTR-PM) and sodium-cooled fast reactors have built the PSA framework, and the framework to finish the PSA analysis. The FHR is compared with the PWR, HTR-PM and sodium-cooled fast reactors from the physics, design and safety. The PSA framework of FHR is discussed. In the FHR, the fuel and coolant combination provides large thermal margins to fuel damage(hundreds of degrees centigrade). The tristructuralisotropic(TRISO) as the fuel is independent in FHR core and its failure is limited for the core. The core damage in Level 1 PSA is of lower frequency. Levels 1 and 2 PSA are combined in the FHR PSA analysis. The initiating events analysis is the beginning, and the source term analysis and the release types are the target. Finally, Level3 PSA is done.

Thermal Performance Test of the Hot Gas Duct of10MW High Temperature Reactor Test Modulegh

he thermal performance test of the horizontal coaxial double tube hot gas duct (HGD) with an internal thermal insulation for the 10MW High Temperature Reactor Test Module (HTR10) was conducted on a Helium Test Loop(HETL). The present paper deals with the technical feature of the HETL, the test section and the thermal performance test of the HGD. The HGD test section with a triple tube structure includes an inner heater, a HGD model and a coldhot gas mixer. A counterflow of cold and hot helium gas under the pressure of about 3.0 MPa and the minimum temperature of 100℃ in the annular passage and the maximum of 950℃ in the central tube of the HGD model was formed. The HGD model was undergone 20 times of pressure cycle test under the pressure ranging from 0.1 to 3.4 MPa, 18 times of the temperature cycle test under the temperature ranging from 100 to 950℃ and high temperature (700 to 950℃) helium flow test for a period of more than 350 hours. The effective thermal conductivity (λeff) of the internal insulation of the HGD was investigated experimentally. The relationship of the effective thermal conductivity with the average tmperature of the internal insulation layer is λeff(W/m/℃)=0.3512+0.0003T(℃). The test results indicate that the HGD model has good abilities to resist heat flux from the central tube to the annular passage, temperature variations, and pressure variations.

Macroscopic Structural Analysis on a 10 kW Class Lab-Scale Process Heat Exchanger Prototype under a High-Temperature Gas Loop Condition

A PHE (Process Heat Exchanger) is a key component in transferring high-temperature heat generated from a VHTR (Very High Temperature Reactor) to a chemical reaction for the massive production of hydrogen. Last year, a 10 kW class lab-scale PHE prototype made of Hastelloy-X was manufactured at the Korea Atomic Energy Research Institute (KAERI), and a performance test of the PHE prototype is currently underway in a small-scale nitrogen gas loop at KAERI. The PHE prototype is composed of two kinds of flow plates: grooves 1.0 mm in diameter machined into the flow plate for the primary coolant, and waved channels bent into the flow plate for the secondary coolant. Inside the 10 kW class lab-scale PHE prototype, twenty flow plates for the primary and secondary coolants are stacked in turn. In this study, to understand the macroscopic structural behavior of the PHE prototype under the steady-state operating condition of the gas loop, high-temperature structural analyses on the 10 kW class lab-scale PHE prototype were performed for two extreme cases: in the event of contacting the flow plates together, and when not contacting them. The analysis results for the extreme cases were also compared.

Gearbox Scheme in High Temperature Reactor Helium Gas Turbine System

Helium Turbine is used in High Temperature Reactor Helium Gas Turbine (HTR-GT) system, by which the direct helium circulation between the reactor and turbine generator system will come true. Between helium turbine and generator, there is gearbox device which reduces the turbine rotation speed to normal speed required by the generator. Three optional gearbox schemes are discussed. The first is single reduction cylindrical gearbox, which consists of one high speed gear and one low speed gear. Its advantage is simple structure, easy to manufacture, and high reliability, while its disadvantage is large volume and misalignment of input and output axle. The second is planetary gear mechanism with static planet carrier. The third is planetary gear mechanism with static internal gear. The latter two gearbox devices have similar structure. Their advantage is small volume and high reduction gear ratio, while disadvantage are complicated structure, many gears, low reliability and low mechanical efficiency.

The AVR as Small Modular Thorium Very High Temperature Reactor:Experiences-Design-Safety-Fuel Cycle

As a young engineer in the power plant department of Brown Boveri,Dr.Schulten had the idea to design nuclear power stations without major risk.The following requirements must be accomplished:ŸA negative temperature coefficient had to avoid an MCA(Maximum Credible Accident);ŸCeramic materials for core construction and fuel elements;ŸA homogenous mixture of nuclear fuel and graphite had to be able to use uranium and thorium as breeding material;ŸThe produced high temperature heat shall be the basis for production of electricity,drinking water,hydrogen,etc.;ŸA relatively simple plant,which could be operated in developing countries,to cogenerate electricity and heat;ŸHelium used as cooling gas.

Long-Term High-Temperature Oxidation of Alloys for Intermediate Heat Exchangers

Alloy 617 is the reference candidate material for high temperature components of gas-cooled reactors, like intermediate heat exchangers. Oxidation tests were performed with two heats of Alloy 617 up to 5000 hours at 950℃ under a simulated helium-cooled reactor environment. Post-treatment examination showed that all materials actually oxidized during the tests with the growth of a surface chromium oxide scale that includes titanium, formation of a carbide-depleted zone underneath the surface, and internal oxidation of aluminum. These oxidation-related phenomena are in good agreement with the data published in the 1980s for Alloy 617 in equivalent testing conditions and were used to assess the alloy corrosion performances. The oxidation kinetics was globally parabolic corresponding to the growth of the external oxide as well as to internal oxidation. In the given test environment, the parabolic rate constants are 0.00090 and 0.00058 mg^2·c^-4m·h^-1 for the two heats of Alloy 617.

HTR-PM二回路图形建模与仿真研究

介绍了在vPower仿真平台上嵌入THERMIX代码来研究紧凑型高温气冷堆仿真机的方法。根据模块式高温气冷堆示范电厂二回路系统的特点和结构,利用vPower仿真平台建立二回路各个系统的组态模型并进行稳态和瞬态仿真结果分析。结果表明,稳态值与设计值的误差均在2%范围内;额定工况下,主调节阀关小和给水流量减少2个典型瞬态响应过程曲线趋势合理,动态响应各项指标及最终稳定值满足要求;循环水泵关闭导致凝汽器循环水中断的事故情况下,因凝汽器真空过低调节主蒸汽阀门迅速关闭,主蒸汽流量减小同时汽轮机跳闸。

HTR-PM蒸汽发生器入口结构对流量分配影响的数值研究

针对高温气冷堆核电站示范工程（HTR-PM）蒸汽发生器实验模型的一回路流量分配进行了数值模拟研究。用Gambit前处理软件建立了数值计算模型并进行网格化处理，通过Fluent流体力学计算软件对没有遮流板和添加不同角度遮流板情况下换热组件出口流量分配均匀性进行模拟分析，结果表明垂直角度的遮流板能够最优地改善流量分配均匀性。同时根据腔体内流速分布，可知由于遮流板的缓冲作用，能够有效缓冲气流对蒸汽发生器内传热管的冲击。计算结果证实了蒸汽发生器内部结构的改进能够改善一回路流量分配均匀性，为-PM蒸汽发生器的设计提供了指导。

HTR-10球形燃料元件制造工艺

10MW高温气冷实验模块堆球形燃料元件的制造技术的研究始于1986年。球形燃料元件的制造使用橡胶模具冷准等静压工艺。目前已完成了制造技术和石墨基体材料的研究和最佳化。已生产了25批,约11000个燃料元件。石墨基体材料的冷态性能符合设计指标,25批燃料元件的平均自由铀含量为5×10-5。

蒙特卡罗方法用于HTR-10首次临界燃料装料预估的校算

在10MW球床式高温气冷实验堆(HTR-10)首次临界前,达到首次临界的堆芯燃料球装量预估是物理设计的一项重要任务。为了确保物理设计的可靠性,引入蒙特卡罗程序MCNP对VSOP程序的计算结果进行校验。根据HTR-10的特点对燃料元件和堆结构,设计出近似而合理的MCNP描述;再选择合理的计算特征值问题的参数,包括跳过的周期数、每周期标定的源数目和得到特征值的周期数;研究燃料球结构的不同描述对keff的影响;确定较优的计算方案。该方案的计算结果表明,在27℃、空气气氛下,MCNP和VSOP程序预估的达到首次临界的总球数分别为16864个和16821个,相对误差为0.25%。HTR-10的首次临界实验表明,预估与实验的结果相对误差小于1.0%。

HTR-10MW电磁轴承转子系统辨识

以高温气冷堆中氦气透平转子的试验模型为研究对象,利用电磁轴承不接触的电磁力实现对转子支承和激励的性质,采用正弦扫频的方式获得高温气冷堆氦气透平转子试验模型转子的频域的分析数据,然后利用模态分析理论获得转子的传递函数和模态振型。从试验结果可以看出,获得的传递函数和模态振型不但验证了理论分析的结果,而且为控制器设计和系统故障检测提供了必要的分析依据。