High-Sensitivity Fast Neutron Detector KNK-2-8M

The design of the fast neutron detector KNK-2-8M is outlined. The results of he detector study in the pulse counting mode with pulses from ²³⁸U nuclei fission in the radiator of the neutron-sensitive section and in the current mode with separation of functional section currents are presented. The possibilities of determination of the effective number of ²³⁸U nuclei in the radiator of the neutron-sensitive section are considered. The diagnostic capabilities of the detector in the counting mode are demonstrated, as exemplified by the analysis of reference data on characteristics of neutron fields in the BR-1 reactor hall. The diagnostic capabilities of the detector in the current mode are demonstrated, as exemplified by the results of measurements of ²³⁸U fission intensity in the power startup of the BR-K1 reactor in the fission pulse generation mode with delayed neutrons and the detector placed in the reactor cavity in conditions of large-scale variation of the reactor radiation fields.     

High-sensitivity fast neutron detector KNK-2-7M

The construction of the fast neutron detector KNK-2-7M is briefly described. The results of the study of the detector in the pulse-counting mode are given for the fissions of ²³⁷Np nuclei in the radiator of the neutron-sensitive section and in the current mode with the separation of sectional currents of functional sections. The possibilities of determining the effective number of ²³⁷Np nuclei in the radiator of the neutronsensitive section are considered. The diagnostic possibilities of the detector in the counting mode are shown by example of the analysis of the reference data from the neutron-field characteristics in the working hall of the BR-K1 reactor. The diagnostic possibilities of the detector in the current operating mode are shown by example of the results of measuring the ²³⁷Np-fission intensity in the BR-K1 reactor power start-ups implemented in the mode of fission-pulse generation on delayed neutrons at the detector arrangement inside the reactor core cavity under conditions of a wide variation of the reactor radiation field.     

Feasibility of creating a specialized reactimeter based on the inverse solution to kinetics equation with a current-mode neutron detector

The file-evaluation results of a reactimeter based on the inverse solution to the kinetics equation (ISKE) are presented, which were obtained using an operating hardware-measuring complex with a KNK-4 neutron detector working in the current mode. The processing of power-recording files of the BR-1M, BR-K1, and VIR-2M reactors of the Russian Federal Nuclear Center—All-Russian Research Institute of Experimental Physics, which was performed with the use of Excel simulation of the ISKE formalism, demonstrated the feasibility of implementation of the reactivity monitoring (during the operation of these reactors at stationary power) beginning from the level of ~5 × 10^–4β_eff.     

压水堆堆芯功率分布在线监测计算中的探测器失效诊断与处理方法

作为堆芯功率分布在线监测计算的重要输入参数，堆内中子探测器的测量数据对堆芯功率分布在线监测具有重要影响，因此在线监测计算中探测器失效的诊断和处理十分必要。采用谐波展开法进行堆芯功率分布的在线监测计算，采用直接观察法、探测器测量值比较法以及探测器重构值比较法分三个阶段对探测器失效进行诊断。基于以上理论，在在线监测系统NECP-ONION中加入探测器失效诊断功能，利用BEAVRS基准题对失效诊断和处理进行验证。数值结果表明，将三阶段的诊断方法结合使用，不仅可以有效判断探测器完全失效的情况，同时对于探测器测量值偏离正常值也具有判断能力。对于探测器失效的处理，NECP-ONION具有较好的探测器失效承受能力。当探测器测量值严重偏离正常值时，程序可诊断其失效并去除错误测量值信息后进行重构；当偏离正常值不足以做出失效诊断时，在线监测程序监测计算精度在可接受范围内。     

加速器驱动次临界系统中堆外中子注量率监测方法（英文）

在加速器驱动的次临界（ADS）系统中,次临界反应堆的功率控制是通过控制束流强度来实现。监测堆外中子注量率,不仅提供了反应堆功率指示,也为反应堆保护系统在启动和运行阶段提供了重要的监测信息,因此,堆外中子注量率的监测在ADS系统的控制与保护中起着非常重要的作用。采用3套裂变室和3套非补偿电离室来监测ADS堆外中子注量率。由于裂变室有脉冲、电流和均方电压3种操作模式,1套裂变室可以监测源量程、中间量程和功率量程等宽范围的反应堆功率。所以,使用的监测方法有3个优点,即:增加了监测通道的冗余度,提高了保护系统的可靠性,以及能提供更多的轴向功率分布信息。由于这些中子探测器对中子能谱很敏感,提出了一种有效的校准方法,即先用一个标准的中子源校准这些中子探测器,然后再将中子注量率除以一个修正因素。基于Geant4仿真结果显示,所提取的裂变室和非补偿电离室的修正因素分别为5和42。In an accelerator driven sub-critical (ADS) system, power control in sub-critical reactor is achieved through the control of the beam current. Excore neutron flux monitoring in an ADS system, not only provides indication of reactor power, but also provides important inputs to reactor protection system during startup and power operation, and thus plays a very important role in the control and protection of ADS system. This paper presents the excore neutron flux monitoring method which uses three fission chambers (FCs) and three uncompensated ion chambers (UICs). With three operation modes, pulse mode, current mode, and mean square voltage mode, an FC can monitor reactor power over a wide range from the source range to the intermediate and power ranges. The proposed monitoring method increases the redundancy of independent monitoring channels, improves the reliability of the protection system, and provides more information on axial power distribution. Since these neutron detectors are sensitive to the neutron energy spectrum, we propose an effective calibration method to provide the exact value of neutron flux, i.e., these neutron detectors are calibrated with a standardized neutron source, and then, a correction factor is added in the calibration by comparing the neutron energy spectrum of the neutron source with that in ADS system. Based on Geant4 simulation, the correction factors of 5 and 42 are extracted for FCs and UICs, respectively.     

压水堆核电站燃料组件弯曲对堆芯中子学的影响分析计算

在压水堆核电站中,由于燃料组件装配的压紧力、冷却剂流动、辐射蠕变、燃耗等因素会导致燃料组件的弯曲,燃料组件的弯曲对组件间的水隙分布产生影响,从而影响中子的慢化行为及堆芯的传热性能,进而对反应堆堆芯的运行参数造成影响。本文分析了组件弯曲的成因及机理、影响及后果（包括对堆芯功率分布、径向功率倾斜、焓升因子、热点因子等参数的影响）,并使用蒙特卡罗软件JMCT,对组件弯曲的确定论计算程序的正确性进行了验证。最后通过确定论的计算程序模块,对CPR1000核电站的组件弯曲情况进行了模拟分析,计算结果表明:在某一燃耗下,随着水隙增加或减小,燃料组件功率会随之增加或减小,使堆芯的功率分布发生倾斜,影响核电站的安全运行。     

Investigation of design parameters in ultrasound reactors with confined channels

This paper presents a three-dimensional numercial simulation of sonochemical degradation upon cavitational activity. The model relates the simulation of the acoustic pressure distribution to the sonochemical reaction rate. As a case study, the thermal degradation of carbon tetrachloride during sonication is studied in a tubular milliscale reactor. The model is used to optimize the reactor diameter, ultrasound frequency and power dissipated to the ultrasound transducers. The results indicate that multiple transducers at a moderate power level are more efficient than one transducer with high power level. Furthermore, the average cavity volume fraction is proposed as a reaction independent parameter to estimate the optimal reactor design. Within the results obtained in this paper, it appears possible to optimise reactor design based on this parameter.     

Fuel breeding in a hybrid muon catalyzed fusion reactor

We discuss the processes of nuclear fuel burnup and plutonium breeding in the uranium blanket of a hybrid mesocatalytic reactor. The time dependence of the nuclear fuel isotopic concentrations was calculated by the BURNFL code. Using a three-dimensional Monte Carlo MORSE-H code the plutonium and tritium breeding coefficients, the fission rates of uranium and plutonium and a specific power distribution in the blanket were computed. The total fusion energy multiplication factor was obtained as a function of the fuel residence time using results of a detailed calculation of the mesocatalytic channel and estimations of the electronuclear channel.     

Program for studying fundamental interactions at the PIK reactor facilities

A research program aimed at studying fundamental interactions by means of ultracold and polarized cold neutrons at the GEK-4-4′ channel of the PIK reactor is presented. The apparatus to be used includes a source of cold neutrons in the heavy-water reflector of the reactor, a source of ultracold neutrons based on superfluid helium and installed in a cold-neutron beam extracted from the GEK-4 channel, and a number of experimental facilities in neutron beams. An experiment devoted to searches for the neutron electric dipole moment and an experiment aimed at a measurement the neutron lifetime with the aid of a large gravitational trap are planned to be performed in a beam of ultracold neutrons. An experiment devoted to measuring neutron-decay asymmetries with the aid of a superconducting solenoid is planned in a beam of cold polarized neutrons from the GEK-4′ channel. The second ultracold-neutron source and an experiment aimed at measuring the neutron lifetime with the aid of a magnetic trap are planned in the neutron-guide system of the GEK-3 channel. In the realms of neutrino physics, an experiment intended for sterile-neutrino searches is designed. The state of affairs around the preparation of the experimental equipment for this program is discussed.     

偏分复用系统中偏振模色散补偿与偏分解复用一体化方案

本文建立了偏分复用系统中偏振模色散与信号偏振态变化引起信道串扰的数学模型, 分析了偏振模色散对偏分复用信道射频功率的影响, 并提出了适用于偏分复用系统的光域偏振模色散补偿与偏分解复用同时进行的方案: 用信道的射频功率作为反馈控制信号, 监测链路中偏振模色散和偏振态变化引起的信道串扰的大小, 用改进的粒子群优化算法对偏振控制器进行自适应控制, 同时完成偏振模色散补偿与偏分解复用. 在112 Gb/s偏分复用-差分正交相移键控(PDM-DQPSK)传输系统中仿真验证了该方案的有效性. 结果表明该方案可以使112 Gb/s-PDM-DQPSK传输系统完成自适应偏分解复用的同时, 在1 dB的光信噪比代价下, 使系统对偏振模色散的容忍度提高20 ps. 关键词： 偏分复用系统 信道串扰 偏振模色散 偏分解复用     

RF generation of the plasma jet channel for the jet PCVD

Breakdown conditions for creation of the hollow cathode discharge in the nozzle passed through the rf powered electrode and creation of the plasma jet channel in PCVD reactor are studied. Pure nitrogen is used for measurements. The creation of jet channel is easier for smaller rf electrodes. The breakdown depends on the pressure and on the gas inflow rate. The plasma potential and the self-bias potential is influenced by the covering of reactor walls and the rf electrode by a dielectric layer.     

堆内黄玉改色装置设计

研制了一种适用于板状燃料堆芯的黄玉改色装置，并对辐照装置的物理安全特性及结构安全特性进行了分析。利用CFD多孔介质模型，获得了改色装置的流场和温度场，确定了功率限制因素，并对装置进行了优化，增强了中子选择材料的冷却能力，结果表明，优化后可在额定功率下进行黄玉改色试验。开展了改色装置的堆外水力学特性实验及冲刷试验，装置工作压差附近的流量试验数据与理论模拟结果差别为-3.6%~1.9%，二者一致，冲刷试验表明，装置对黄玉残渣有很强的包容、收集效果，不会导致燃料元件流道堵塞。     

光纤光栅在干式空心电抗器固化中的测温研究

采用埋入式光纤Bragg光栅温度传感器,实现了对干式空心电抗器固化过程中各包封层的温度监测。在制作过程中,将温度传感器埋在干式空心电抗器导线外包封表面,连接光纤从电抗器上沿引出。电抗器绕线与包封完成后放入干燥室内固化,监测电抗器各包封层在固化过程中的温度变化。通过监测得到了电抗器各包封温度变化的曲线图,当炉温示值稳定在140℃时,各包封温度低于预期,分布在105~125℃之间,且由外向内逐渐降低。通过对干式空心电抗器固化过程中的温度进行监测,可实时了解并改进干燥固化过程中出现的问题,对保证电抗器的质量及安全具有重要意义。     

Parameter space map of an electron cyclotron resonance plasma in acompact chamber

Ion current density measurements were made in an electron cyclotron resonance (ECR) plasma reactor for both argon and oxygen discharges. Spatial changes in the ion current density were also recorded across the reactor diameter for changes in pressure and power. These measurements revealed a minimum in the ion current density on the reactor axis. This observation has been explained as a consequence of the shape of the ECR region, which, in turn, is dependent on the mode of coupling. Current density measurements were made as a function of reactor pressure and microwave power for two different axial locations in the system. A Langmuir probe was also used at these two locations to measure the electron temperature as a function of these process conditions. It was observed that the ion current density and/or plasma density measured downstream from the ECR zone, increased significantly in the low-pressure/high-microwave power region. Results from this region of the operating parameter space have not previously been reported. Further existing models do not predict this observed increase in plasma density or ion current density. It has been proposed that a rarefication of the gas in the ECR region, as a result of gas heating, has acted to increase the outward diffusion of electrons from the ECR zone and, thus, has increased the ambipolar diffusion of ions to the downstream location. This proposal has been partially validated by experimental results in which the ion energy was measured as a function of reactor pressure and gas flow rate. The shape of the oxygen parameter space map differs significantly from that for Ar. The principal reasons for these changes are a number of different inelastic electron scattering mechanisms which effect the transport electrons out of the ECR zone and through ambipolar diffusion also the transport of ions. The second factor is the production of negative ionic species which varies with reactor pressure and, thus, T_e     

UWTOR-M?a Conceptual Design Study of a Modular Stellarator Power Reactor

A preliminary design of a 5500 MWth modular stellarator power reactor, UWTOR-M, is presented. Discrete twisted coils are used in an Q = 3 configuration with maintainability as a prime consideration. The natural steliarator divertor is used for impurity control in conjunction with innovative high performance divertor targets. A unique blanket design is proposed which minimizes the overall tritium inventory in the reactor. Finally, a scheme for maintaining the first wall/blanket and other reactor components is discussed.     

Determination of the relative power density distribution in a heterogeneous reactor from the results of measurements of the reactivity effects and the neutron importance function

A method for experimental determination of the relative power density distribution in a heterogeneous reactor based on measurements of fuel reactivity effects and importance of neutrons from a californium source is proposed. The method was perfected on two critical assembly configurations at the NARCISS facility of the Kurchatov Institute, which simulated a small-size heterogeneous nuclear reactor. The neutron importance measurements were performed on subcritical and critical assemblies. It is shown that, along with traditionally used activation methods, the developed method can be applied to experimental studies of special features of the power density distribution in critical assemblies and reactors.     

Near infrared imaging of micro-structured polymer-metal surface pattern

Two-dimensional infrared scanning microscopy images of micro-structured surface patterns in an organic transistor device with metal electrode stripes on a polymer channel layer have been demonstrated. A compact single mode optical fiber scanning probe which has a micro dome-shape lens at the tip end was used for the scanning in which reflected beam intensities are coupled back to the optical fiber transceiver depending on the returned power of the sample material. Based on the experiment, the obtained structural dimensions of the micro structure specimen were well matched to the designed ones. These images were compared to the digital microscopy photos for a potential usage to conduct not only the in situ microscopic electrode pattern monitoring of the device but also to non-destructively investigate any surface reflecting material in micrometer scales.     

Neutron Fourier diffractometer FSD for residual stress studies in materials and industrial components

Neutron diffraction study of residual stresses in materials became widely used in the world due to high penetrating power of neutrons. Therefore, to study residual stresses, the FSD (Fourier stress diffractometer) was developed at the IBR-2 reactor channel (Frank Laboratory of Neutron Physics, Joint Institute for Nuclear Research, Dubna, Russia), which, due to a special correlation technique (a fast Fourier chopper for modulating the primary neutron beam intensity and the RTOF method for data acquisition) makes it possible to obtain high-esolution diffraction spectra Δd/d = 4 × 10^-3. This diffractometer was developed taking into account world experience in the study of residual stresses in materials; experience in the development of such devices in Russia and abroad was also used. The FSD diffractometer itself and its current state are described.     

Automatic gain control in Raman amplifier with multi-wavelength pumps

Automatic gain control method in Raman amplifier with multi-wavelength pumping scheme is presented. Monitoring of several channel power and feedback pump control is used in the gain control method. The condition to minimize the gain deviation is investigated by numerical simulation. Two monitoring channels are necessary to confine gain deviation in ±0.2 dB at two pumps C-band Raman amplifier. In the experiment, gain deviation of 1.5 dB is controlled to 0.2 dB at 38/40 channels drop, and fast suppression of transient gain excursion is achieved.     

A new reactor for process intensification involving the simultaneous application of adjustable ultrasound and microwave radiation

Ultrasound (US) and Microwaves (MW) are effective methods for processes intensification. Their combined use in the same reactor can lead to remarkable results. Recently there has been a resurgence of interest in this field for new synthetic applications using reactors based upon existing technologies. We describe here a new type of apparatus in which the thermal energy is continuously removed from the system making possible the use of high power and adjustable ultrasonic and microwave densities throughout the process. The installation consists of a glass reactor located in a monomode applicator which is immersed at the same time in an ultrasonic device which can be operated at different frequencies and powers. A liquid, transparent to microwaves, was used to couple ultrasonic energy to the reactor and to remove the heat generated. Comsol software was used to get information about the distribution of ultrasonic and microwave energy between the reactor liquid and the coupling fluid. The performance was assessed using the conversion of p-nitrophenol into 4-nitrocatechol as a chemical dosimeter and a transesterification.