Determination of critical mass and neutron flux distribution by means of physical models

The design of nuclear reactors, especially new reactors, requires experimental measurements in order to obtain accurate values of the pertinent parameters. In the present paper we present a new method for the preliminary determination of the critical mass of a reactor and the neutron flux distribution; this method is based on the use of physical models. In carrying out these experiments use is made of a model of the reactor which does not contain fissionable material. The working channels in the model are filled with a neutron absorber whose cross section simulates the absorption cross section for neutrons in the fissionable material. The production of fast fission neutrons is simulated by means of a neutron source which is moved along the channels. The distribution of thermal neutrons is measured by means of detectors which are sensitive to thermal neutrons. If the source strength and the absolute value of the neutron flux are known, it is possible to find the critical mass of the reactor.This method has been checked in a reactor with uranium hexafluoride. The value of the critical mass found experimentally was found to be in good agreement with the value obtained when the reactor was started up.The proposed method can also be useful in preliminary investigations of reactor designs, the choice of optimum lattice parameters, etc. The technique is extremely simple and does not require fissionable material or high neutron fluxes.     

利用金属钆测量热中子通量的实验研究

研究了一种测量热中子通量的新方法,利用金属钆与热中子反应产生的次级γ射线来确定热中子通量。使用两个NaI探测器进行符合测量,设计了对伽玛射线和散射中子的良好屏蔽体。经过对本底和钆样品的多次测量,对钆与中子反应产生的伽玛能谱进行了分析,计算出了中子与钆反应产生的计数率(样品净计数率),其最大值达到2.74 Hz,从而证实了这种方法的可行性。     

用钴活化法测定反应堆中热中子积分通量

本文叙述了用钴活化法测定高通量堆中热中子积分通量的方法。测得的热中子积分通量值与计算值作了比较。本法适于测定在高通量堆中长期辐照的较高热中子积分通量。     

Experimental investigation of the two-phase flow distribution in the outlets of a horizontal multi-branch header

An experimental investigation was conducted to study the two-phase flow distribution in a horizontal header with two inlet turrets and 30 (six banks of five) outlet branches. Tests were performed using air–water mixtures at room temperature and a nominal header pressure of 170.3 kPa. The test matrix included one- and two-turret injection, two inlet water flow rates and four different air flow rates for each water flow rate, giving four different inlet qualities. The outlet flow rates of air and water were measured in all the branches under the condition of equal pressure drop across all branches. The data show that there is significant variation in air and water flow rates among the branches, both in the axial and circumferential directions. The flow distribution among the branches was found to be strongly dependent on the inlet flow rates of air and water, and the type of injection (one or two turrets).     

HT-7超导托卡马克装置上中子通量分布的实验研究

本文介绍了HT-7超导托卡马克装置上中子通量分布的测量实验.在实验中,使用了两种有较强抗伽马能力的中子探测系统:BF3和3He正比计数管及其相应的电子学与数据采集.在2005年春季实验中,在相同实验条件下,细致测量并比较研究了真空室外不同水平位置、垂直位置的中子通量.实验研究了真空室窗口和变压器铁芯的存在对测量结果的影响,验证了测量结果与三维数值计算的一致性.本项工作为更深入的物理研究奠定了基础.     

The neutron flux in a spherical void

Using the basic theory developed in our earlier work (Cassell, J.S., Williams, M.M.R., 2005. Particle flux in an annular gap about a sphere, Annals of Nuclear Energy 32, 457, we have evaluated the neutron flux across a spherical void due to a point source in a moderating and absorbing medium. Neutron motion in the moderator is described by diffusion theory and that in the void by the free streaming Boltzmann transport equation. An explicit solution is obtained in the form of an infinite series. This is evaluated numerically for a number of practical cases and comparison is made with an exact transport calculation using a Monte Carlo code. The hybrid method is seen to be highly accurate.     

Development of a data acquisition and control system for the International Thermonuclear Experimental Reactor neutron flux monitor

To satisfy high-precision, wide-range, and real-time neutron flux measurement requirements by the International Thermonuclear Experimental Reactor(ITER), a data acquisition and control system based on fission chamber detectors and fast controller technology, has been developed for neutron flux monitor in ITER Equatorial Port #7. The signal processing units which are based on a field programmable gate array and the PXI Express platform are designed to realize the neutron flux measurement with 1 ms time resolution and a fast response less than 0.2 ms,together with real-time timestamps provided by a timing board. The application of the widerange algorithm allows the system to measure up to 10~(10) cps with a relative error of less than 5%.Furthermore, the system is managed and controlled by a software based on the Experimental Physics and Industrial Control System, compliant with COntrol, Data Access and Communication architecture.     

DORT程序进行RPV中子注量率计算的可靠性验证

反应堆压力容器(RPV)中的碳钢材料受到快中子辐照会发生性能变化。为了防止由于RPV的材料性能发生变化而不适当地限制核电厂的运行,需要限定核电厂寿期内RPV中的最大快中子注量,并且要求安装辐照监督管对RPV材料所受到的快中子注量进行监督。因此,RPV和辐照监督管中子注量率的精确计算对RPV的辐照安全和寿命管理具有十分重要的意义。三代非能动压水堆核电厂主要采用基于BUGLE-96截面库的二维离散纵标法程序DORT进行RPV中子注量率计算。本文利用秦山核电厂第五根辐照监督管的中子注量率测量数据和MCNP-4B计算结果与DORT程序的计算结果进行比较,来验证采用DORT程序进行RPV母材段中子注量率计算的可靠性。     

Experimental analysis for neutron multiplication by using reaction rate distribution in accelerator-driven system

Basic experiments are carried out in the Kyoto University Critical Assembly (KUCA) to study the nuclear characteristics of the accelerator-driven systems (ADS) and to establish a new neutron source for research. A method for measuring the neutron multiplication in the subcritical system is proposed by utilizing the reaction rate distribution obtained by the optical fiber detector. A comparison between the measured and calculated neutron multiplication shows agreement within a relative difference of 5% in most cases, through introducing certain correction factors.     

Visualization and measurement of two-phase flow by using neutron radiography

To apply neutron radiography (NR) technique to fluid research, high frame-rate NR with a steady thermal neutron beam has been developed in the present research program by assembling up-to-date technologies for neutron source, scintillator, high-speed video and image intensifier. This imaging system has many advantages such as a long recording time (up to 21 min), high-frame-rate (up to 1000 frames s⁻¹) imaging and no need for triggering signal. Visualization of air-water two-phase flow in a metallic duct was performed at the recording speeds of 250, 500 and 1000 frames s⁻¹. The qualities of those consecutive images were good enough to observe and measure the flow structure and the characteristics. It was demonstrated also that some characteristics of two-phase flow could be measured by using the present imaging system. Image processing technique enabled measurements of various flow characteristics in two ways. By utilizing geometrical information extracted from NR images, data on flow regime, rising velocity of bubbles, and wave height and interfacial area in annular flow were obtained. By utilizing attenuation characteristics of neutrons in materials, measurements of void profile and average void fraction were performed. It was confirmed that this new technique may have significant advantages both in visualizing and measuring high-speed fluid phenomena when the other methods such as an optical method and X-ray radiography cannot be applicable.     

Experimental investigation and CFD simulation of horizontal stratified two-phase flow phenomena

For the investigation of stratified two-phase flow, two horizontal channels with rectangular cross-section were built at Forschungszentrum Dresden-Rossendorf (FZD). The channels allow the investigation of air/water co-current flows, especially the slug behaviour, at atmospheric pressure and room temperature. The test-sections are made of acrylic glass, so that optical techniques, like high-speed video observation or particle image velocimetry (PIV), can be applied for measurements. The rectangular cross-section was chosen to provide better observation possibilities. Moreover, dynamic pressure measurements were performed and synchronised with the high-speed camera system.CFD post-test simulations of stratified flows were performed using the code ANSYS CFX. The Euler–Euler two fluid model with the free surface option was applied on grids of minimum 4 × 10⁵ control volumes. The turbulence was modelled separately for each phase using the k–ω-based shear stress transport (SST) turbulence model. The results compare very well in terms of slug formation, velocity, and breaking. The qualitative agreement between calculation and experiment is encouraging and shows that CFD can be a useful tool in studying horizontal two-phase flow.     

Experimental investigation of mass exchanges between two laterally interconnected two-phase flows

The hydrodynamic behaviour of two laterally interconnected subchannels under two-phase flow conditions has been studied. For equal liquid mass flow rates in the channels at the beginning of the interconnected region but substantially different void fractions, the key parameters: void fraction, liquid and gas mass flow rates and pressures have been determined in both channels along the interconnection.The experimental results on void fractions, liquid mass flow rates and pressures in the channels have been compared with the predictions of the COBRA-III-C and COBRA-IV subchannel computer codes and in general a reasonable agreement has been obtained.