Hydrogen Permeation through Incoloy-800

The poloidal distribution of the first wall 14 MeV neutron flux and the tritium breeding ratio in a Tokamak fusion reactor were calculated using Monte Carlo method. The poloidal distribution of the 14 MeV neutron flux in the first wall was found to be quite different from that of the primary incident flux. The tritium breeding ratio calculated by the Monte Carlo method became about 5% larger than the value obtained from S_N transport calculations.     

BN-800 design validation and construction status

Information is presented on the BN-800 design, the second design following BN-600, power-generating unit with a fast reactor. The main stages of the development of the design begun in the 1980s, modified in the 1990s after the Chernobyl accident, and accepted for construction within the government program starting in 2000 are presented. The fundamental differences of BN-800 from BN-600 are characterized, and current R&D work is briefly described. Information is presented on the construction of BN-800 at the Beloyarskaya nuclear power plant, where the BN-600 has been operating since 1980.     

800MSPS FADC数据采样系统的研制

本文开发了一种基于MAX105 800MSPS 6bit FADC和FPGA的高速数据采样系统.FADC的输出通过FPGA中的串并转换电路降低到1OOMHz,便于后续数据处理和传输.FPGA还实现了数据缓存、自甄别触发以及压缩和时间信息获取等功能.经过压缩和缓存的数据由TELL1采集并传送计算机,最大数据带宽可达4Gbps.     

I-800合金微动磨损特性研究

使用PLINT微动磨损试验机研究了核电材料I-800合金在常温、法向载荷为50 N和80 N、位移幅值2~40 μm,圆柱交叉接触模式下的切向微动磨损特性.结果表明,在相同载荷下,随位移幅值增加,I-800合金微动运行经历了从部分滑移区向混合区和滑移区的规律性转变.混合区和滑移区的摩擦系数高于部分滑移区.部分滑移区微动磨损轻微,接触区域边缘的微滑区出现微裂纹;滑移区磨损严重,磨痕面积和磨损体积较大;混合区磨屑聚集滞留现象明显.I-800合金的微动磨损机制以摩擦氧化和磨粒磨损为主要特征.     

The waveguide system of the HLS 800 MeV Linac

To upgrade Hefei Light Source(HLS) Linac, eight accelerating units have been constructed to realize fullenergy injection of the storage ring. Each of the units consists of two 3-m accelerators driven by one klystron.The input cavity detuning method was developed to measure and correct the phase length of the RF power distribution waveguide system. The design of the waveguide network and the principles of the detuning method are presented in this paper. After correction, the phase error between the waveguide of the two accelerators was less than ±0.5?, and the maximum electron energy of Linac reached 805 MeV, which is very near the theoretical maximum value of 810 MeV. These results demonstrate that the calibration of the waveguide was successful.     

PMS-800大流量大气颗粒物采样器的研制

大气颗粒物采样器是《全面禁止核试验条约》(CTBT)中放射性核素监测的关键设备之一。结合实验室实际情况,成功研制了PMS-800大流量大气颗粒物采样器。PMS-800采用变频技术保持流量稳定,自动控制软件可实现采样过程的控制、数据采集和数据处理功能;用聚丙烯纤维滤材作为颗粒物的收集介质。对采样器的性能测试结果为:最大采样流量可达800 m3.h-1以上,流量不确定度小于5%;采样期间流量波动在±5%之内;当负载达到20 kPa时,实现停机保护;采样滤材对0.2μm气溶胶的收集效率为82.5%;自采样开始每10 min存储一次系统参数。该采样器满足CTBT相关技术文件的要求。     

Investigations on Inconel 718 irradiated with 800 MeV protons

In spallation sources, the neutrons (utilized as probes for condensed matter research or for inducing nuclear transmutations) are generated by protons of around 1 GeV energy which cause spallation of the nuclei in a heavy metal target. The beam powers of the proposed future facilities are in the range of 1 to several 10 MW and the corresponding high particle fluxes make radiation damage the crucial effect for the lifetime of target structural materials in or close to the proton beam. In order to establish a database on spallation-relevant radiation effects, post-irradiation investigations of components of spent targets from operating medium power sources are being performed. Here we report first results on Inconel 718 irradiated in LAMPF up to a fluence of 3 × 10²⁵ p/m². Microhardness and bending tests together with SEM and TEM investigations show a considerable degradation of the mechanical properties of the material requiring additional highly controlled tests, now underway, to determine fracture toughness and tensile properties as a function of dose.     

Intrinsic Safety of Future BN-800 Based Nuclear Technology

More than 40 years of experience in performing research and development work and operation of fast sodium-cooled reactors is analyzed. It is shown that such reactors possess a system of intrinsic safety properties, making possible long-time reliable operation and reducing to a minimum the consequences of an accident.A BN-800 unit under construction with the core switched to nitride fuel can serve as a basis for nuclear technology with intrinsic safety in accordance with the requirements of the strategy for the development of nuclear power in Russia in the first half of the 21st century.     

800MeV电子储存环VME总线ramping板的研制

介绍了合肥国家同步辐射实验室８００ＭｅＶ电子储存环主电源控制系统中ＶＭＥ总线ｒａｍｐｉｎｇ板的设计及研制过程。     

800H合金长时间蠕变下的显微组织

对低负荷长时间蠕变试验下800H合金显微组织的研究表明:空洞在晶界M_(23)C_6碳化物的一侧形成,微裂纹通过一连串这样的小空洞而发展;晶界M_(23)C_6碳化物和相邻两晶粒之一有共格关系而与另一晶粒无共格界面,共格界面强化了晶界,这一强化作用可用蠕变激活能的提高来说明,晶界还有G相析出,但未发现合金中有γ'相的形成。合金能长时间保留网状的位错结构,晶界碳化物附近有位错塞积,亚晶界结构发展不充分,这与典型的回复蠕变是不同的。     

Behavior of vibrationally compacted mixed fuel in BN-800

The modified computer code MACROS was used to study the behavior of fuel elements with vibrationally compacted mixed fuel under irradiation in BN-800. Verification calculations were performed for fuel elements irradiated in BN-600 under close to nominal conditions. Attention was focused mainly on the factors playing an important role in their serviceability: swelling, creep, corrosion behavior of cladding, temperature distribution, gas-release, and degree of structural reformation of the fuel core.     

HLS800MeV直线加速器相位控制系统的研制

介绍了合肥光源(HLS)800 MeV直线加速器相位控制系统的研制进展,该系统包括相位稳定系统和相位翻转系统两部分。其中前者主要由I/Q解调器、电控移相器和虚拟示波器等组成;后者由脉冲信号发生器和I/Q调制器组成。目前样机制作已完成,测试表明前者的相位分辨率为±0.1°,在线测量精度为±0.3°,闭环相位稳定度可达±0.5°;后者的精度为(180±2)°,样机各项参数均达到设计指标。     

An aging assessment on ex-service Alloy 800 steam generator tubing

To support SG life extension and plant life management, an aging assessment was performed on a number of ex-service Alloy 800 steam generator (SG) tubes removed from three CANDU^®1 stations with service life spanning from 2 to 27 years. Laboratory tests and examinations were carried out to investigate the potential aging mechanisms of SG tubing. High-temperature electrochemical experiments were performed under simulated SG secondary side crevice chemistry conditions to determine the corrosion susceptibility of the ex-service tubing; metallurgical examinations were carried out to check the chemical compositions, grain size, and hardness of the ex-service tubing materials and secondary ion mass spectrometry (SIMS) analysis was performed to assess the potential surface chromium depletion and grain boundary segregation of the ex-service tubing. Based on the results from the assessment, no increase in the corrosion susceptibility or changes in metallurgical properties of the ex-service tubes resulting from aging were observed. SIMS top-down profiles did not detect any aging-related surface chromium depletion on any of the ex-service tubes. However, SIMS imaging performed on the polished cross-sections of the ex-service tubes observed boron precipitation at the grain boundaries. Since no archived tubing with the same heat number as that of the ex-service tubing is available for comparison, whether the boron precipitation at grain boundaries is attributed to aging through SG operation is not conclusive and needs further clarification. In addition, the impact of this boron precipitation on the integrity of Alloy 800 SG tubing needs further investigation.     

Carburization and tensile behavior of alloy 800 in liquid sodium

The carbon transfer has been analyzed in the Alloy 800/sodium/stainless steel system by determining the carbon-uptake of Alloy 800 foils, which were exposed in liquid sodium of known carburizing potential. p ]Under equilibrium conditions between 650 and 550°C the measured total carbon concentrations in the Alloy 800 labs were found to be roughly related to the carbon activities of the sodium environment by the equation already stated for the $\text{18Cr-}\text{8}\text{10}$ Ni stainless steels, extrapolated to the chemical composition of the Ni-rich austenitic alloy. However the Alloy 800 was not found to undergo any decarburization in low-carbon activity environments. The carbon diffusion kinetics was determined as a function of temperature, it was found to be similar to that reported for the AISI-304 type of steel. p ]The effects of sodium exposure on microstructural and mechanical properties of several Alloy 800 heats were examined at 550°C as a function of the active carbon concentration in the sodium and of the $\text{Ti}\text{C}$ ratio in the alloys.     

FH1919(DD-800)多道脉冲分析系统

本文叙述了FH1919(DD-800)多道脉冲分析系统硬件和软件的功能及特点,对高速数据获取接口(DMA)的组成和工作过程作了描述,对支持谱仪系统的功能驱动软件(MCA)的逻辑结构、能谱曲线显示程序作了介绍。     

Incoloy－800抗钠水反应耗损特性研究

报道了在ＳＷＡＴ－２￣＊试验回路上进行的Ｉｎｃｏｌｏｙ－８００抗钠水反应耗损特性研究结果。内容包括：耗损速率（Ｗ＿Ｒ）与水泄漏率（Ｇ）及与水泄漏孔到被耗损管子表面距离（Ｌ）的关系。导出Ｗ＿Ｒ与Ｌ，及Ｇ关系的经验公式，结果表明Ｉｎｃｏｌｏｙ－８００具有良好的抗钠水反应特性。     

PWR一回路水质中800合金的腐蚀研究

用320℃含600 mg/kg硼和2 mg/kg锂的高氧含量水溶液模拟PWR一回路水质,研究了800合金在一回路水中的腐蚀特性。结果表明,800合金试样在被侵蚀1500 h之后,表面生成一层很薄的氧化膜,去除氧化膜后,计算出其均匀腐蚀速率为4.03×10?4 mm/a,基体中TiN缺陷处容易引起点蚀,管状试样内环出现明显的晶间腐蚀现象。     

Evaluation of anelasticity and plastic creep limit for alloy 800

The elevated temperature tensile, anelastic and creep properties of a precipitation strengthened Ni---Cr austenitic steel (alloy 800) have been evaluated with respect to LMFBR application. These properties have been estimated and formulated for small strains and temperatures on the order of 823 K. It has been shown that despite suppression of the in-service stresses to beneath the alloy's yield strength, plastic deformation will occur at such temperatures and the stress below which plastic strain is effectively zero (plastic creep limit) is negligible for a reactor life time. The plastic creep limit at a given time and temperature markedly depends on the degree of precipitation hardening or prior cold deformation for alloy 800. The contribution from anelastic deformation is less than 0.05% and only becomes important for strict dimensional control and constrained parts.