Experimental validation of the modified linear scaling methodology for scaling ECC bypass phenomena in DVI downcomer

In the direct vessel injection (DVI) system downcomer, the direct emergency core coolant (ECC) bypass is activated during the reflood phase of a large-break loss-of-coolant accident (LBLOCA) by the interaction between the downward-flowing liquid-film and the transverse gas flow. Direct ECC bypass is reportedly the major bypass mechanism of ECC, and various experiments have been performed to obtain detailed information about the ECC bypass in a DVI downcomer. These lead to a proposed new scaling methodology, named ‘modified linear scaling’, which is expected to preserve the phase distribution in the downcomer and the ECC bypass phenomena. In the present study, modified linear scaling was experimentally validated in air–water tests comprising Test 21-D of the upper plenum test facility (UPTF). The counterpart tests of UPTF Test 21-D were performed in 1/7.3 and 1/4.0 scale models of a UPTF downcomer, and the test results were compared with the experimental data of UPTF Test 21-D. Two important parameters of direct ECC bypass – the normalized liquid-spreading width on the downcomer wall and the direct ECC bypass fraction, which is the fraction of input water bypassed out the broken cold-leg – were considered in the validation. The comparison revealed that the scaling parameters of direct ECC bypass are well preserved in the prototype and reduced models, from which we conclude that the modified linear scaling methodology is appropriate for designing a reduced test facility and for a scaling analysis of direct ECC bypass in the reflood phase of an LBLOCA.     

Counterpart Tests of SBLOCA on the Effect of Break Location with the ATLAS: DVI Nozzle versus Cold-Leg Breaks

Results from two integral effect tests were compared to discuss the effect of break location between the direct vessel injection (DVI) nozzle and cold leg during the small-break loss of coolant accident (SBLOCA) scenario. One is the SB-DVI-09 test for a 6-inch (50% break area of a DVI nozzle) DVI line break and the other is the SB-CL-06 test for an equivalent break size of cold leg. Both counterpart tests were performed with the same control logic and initial/boundary conditions except for different break locations of the DVI line and cold leg. Experimental results showed that the maximum heater surface temperature increased more with the broken DVI nozzle (SB-DVI-09) than with the broken cold leg (SB-CL-06) due to the delayed and simultaneous occurrence of the loop seal clearing and the momentary decrease in the collapsed water level in the core region.     

Effect of depressurization on reactor vessel inventory in the absence of ECCS injection

A series of tests were performed to evaluate inventory depletion as a reactor vessel undergoes depressurization in the absence of any emergency core coolant system injection (ECCS). These tests were carried out in a scaled representation of a reactor vessel which was initially filled with saturated water up to the elevation of the hot legs. Depressurization valves installed on take-off lines from the hot legs were opened and level swell ensued in the reactor vessel initiating a two-phase blowdown. This was followed by subsequent single-phase discharge transient which in some cases led to core uncovery. A combined model encompassing the two-phase and single-phase discharge portions of the transient is proposed. The inventory-versus-pressure traces obtained from the model compare well with the experimental results. These traces are discussed as bounding trajectories for a large class of small break loss of coolant accident (LOCA) transients which otherwise must be considered individually.     

Effect of steam condensation on countercurrent flow limiting in nearly horizontal two-phase flow

An analytical model that includes the steam condensation effect has been derived and a parametric study has been performed. In addition, a series of experiments were performed and a total of 34 experimental data for the onset of countercurrent flow limiting (CCFL) in nearly horizontal countercurrent two-phase flow have been obtained for various flow rates of water. Comparisons of the present CCFL data with slug formation models show that the agreement between the present as well as the existing model and the data is about the same. However, the deviation between Taitel and Dukler’s model predictions and the data is the largest when j_f<0.04 m s⁻¹. A parametric study of the effect of condensation using the present model shows that, when all local conditions are similar, the model predicted local gas velocities that cause the onset of flooding are slightly lower when condensation occurred. Based on the visual observation and the evaluation of the present work, it has been concluded that the criterion derived for the onset of slug flow can be directly used to predict the onset of inner flooding in nearly horizontal two-phase flow within the experimental ranges of the present work.     

一种基于概率判决的强纠错卫星数据存储编码

单粒子翻转可能造成星载电子系统的损伤,甚至使之失效.本文针对解决皮卫星数据存储的可靠性问题,提出一种新的纠错编码:交叉正反码,并将之与常用的三倍冗余判决(TMR)技术进行了比较研究.     

冲击磁铁误差对注入过程的影响

简要说明合肥同步辐射光源（ＨＬＳ）的储存环新注入系统,分析由于冲击磁铁的误差而产生的非理想凸轨以及对注入过程的影响。针对ＨＬＳ的三种运行模式进行计算机模拟,从而确定冲击磁铁的误差极限。     

基于天然μ子散射特征评估铀板内水平狭缝宽度的方法

针对经典μ子成像方法用于特殊对象结构探测的技术难点,提出了一种通过直接比较对象发生结构变化前后μ子散射特征的差异来进行形变类型和尺度判定的新思路,称为正向参比法。相比于经典的逆向反演法,该方法在原理上对于初始结构已知的特殊核对象的结构变化探测更有优势。从初步模拟结果来看,在合理的天然μ子通量下,该方法可实现铀板内亚毫米尺度水平狭缝的存在及其尺度的准确判定。     

Effect of non-condensable gas and wavy interface on the condensation heat transfer in a nearly horizontal plate

An experimental study was conducted to investigate the effect of non-condensable gas and wavy water film on condensation heat transfer. The experiment was performed in a nearly horizontal (4.1°) square duct of 0.1 m height, 0.15 m width and 1.52 m length at atmospheric pressure. A water film in a steady thermal condition was injected to simulate the effect of a wavy interface on the condensation. The experimental data for the heat transfer coefficient and the interfacial structure of the wavy condensate were obtained along with the three parameters: air mass fraction, mixture velocity and film flow rate. When the interface is smooth, the heat transfer coefficients with or without non-condensable gas agree reasonably with the previous theories. The waviness of condensate film increases the heat transfer up to several tenths of a per cent.     

电子入射角对束流传输系数和能量沉积的影响

利用数值方法研究了不同能量 (0 .4— 1.4MeV)的电子束以不同的入射角穿透不同厚度碳靶的束流传输系数和能量沉积。计算结果表明 ,随着电子束入射角的增大 ,束流的传输系数减小 ,而较小入射角 (接近垂直入射角 )的电子在靶材料中穿透深度更大 ;能量为 1.0— 1.4MeV的电子束当入射角在 6 0°— 70°时在碳靶单位体积中沉积的能量最大     

Direct vessel inclined injection system for reduction of emergency core coolant direct bypass in advanced reactors

Multidimensional thermal hydraulics in the APR1400 (Advanced Power Reactor 1400 MWe) downcomer during a large-break loss-of-coolant accident (LBLOCA) plays a pivotal role in determining the capability of the safety injection system. APR1400 adopts the direct vessel injection (DVI) method for more effective core penetration of the emergency core cooling (ECC) water than the cold leg injection (CLI) method in the OPR1000 (Optimized Power Reactor 1000 MWe). The DVI method turned out to be prone to occasionally lack in efficacious delivery of ECC to the reactor core during the reflood phase of a LBLOCA, however. This study intends to demonstrate a direct vessel inclined injection (DVII) method, one of various ideas with which to maximize the ECC core penetration and to minimize the direct bypass through the break during the reflood phase of a LBLOCA. The 1/7 scaled down THETA (Transient Hydrodynamics Engineering Test Apparatus) tests show that a vertical inclined nozzle angle of the DVII system increases the downward momentum of the injected ECC water by reducing the degree of impingement on the reactor downcomer, whereby lessening the extent of the direct bypass through the break. The proposed method may be combined with other innovative measures with which to ensure an enough thermal margin in the core during the course of a LBLOCA in APR1400.     

Effect of water injection on hydrogen generation during severe accident in PWR

Effect of water injection on hydrogen generation during severe accident in a 1000 MWe pressurized water reactor was studied.The analyses were carried out with different water injection rates at different core damage stages.The core can be quenched and accident progression can be terminated by water injection at the time before cohesive core debris is formed at lower core region.Hydrogen generation rate decreases with water injection into the core at the peak core temperature of 1700 K,because the core is quenched and reflooded quickly.The water injection at the peak core temperature of 1900 K,the hydrogen generation rate increases at low injection rates of the water,as the core is quenched slowly and the core remains in uncovered condition at high temperatures for a longer time than the situation of high injection rate.At peak core temperature of 2100-2300 K,the Hydrogen generation rate increases by water injection because of the steam serving to the high temperature steam-starved core.Hydrogen generation rate increases significantly after water injection into the core at peak core temperature of 2500 K because of the steam serving to the relocating Zr-U-O mixture.Almost no hydrogen generation can be seen in base case after formation of the molten pool at the lower core region.However,hydrogen is generated if water is injected into the molten pool,because steam serves to the crust supporting the molten pool.Reactor coolant system (RCS) depressurization by opening power operated relief valves has important effect on hydrogen generation.Special attention should be paid to hydrogen generation enhancement caused by RCS depressurization.     

Effect of finite sample dimensions and total scatter acceptance angle on the gamma ray buildup factor

The simultaneous variation of gamma ray buildup factors with absorber thickness (up to 6.5 mfp) and total scatter acceptance angle (which is the sum of incidence and exit beam divergence) in the media of high volume flyash concrete and water was studied experimentally using a point isotropic ¹³⁷Cs source.     

Effect of self-ion injection in simulation studies of void swelling

The rate theory of void swelling is generalized to incorporate the effect of excess interstitial production resulting from self-ion injection in simulation studies. The swelling rate is shown to be reduced at all temperatures, the fractional reduction being largest in the region where intrinsic recombination of irradiation-induced interstitials and vacancies dominates, provided there is no dislocation recovery at high doses. When such recovery processes are operative, however, the effect of self-ion injection is most important near the peak swelling temperature and can lead to a saturation in swelling with increasing dose which, in the model considered, would be absent under neutron irradiation. For this reason it is emphasized that the results of simulation experiments, without complementary microstructural data, should be viewed with caution as far as their quantitative relation to neutron damage is concerned.     

Correlations for the penetration of ECC water in a model of a PWR downcomer annulus

The application of dimensional analysis to the partial penetration data on the Battelle models (1/15 and 2/15 scales) results in a better fit of the penetration data than previous correlations. This analysis predicts the fractional penetration of ECC water into the lower plenum from the water flow rate, liquid subcooling and system pressure, in terms of Froude numbers based on superficial velocities of steam and water.     

Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR™: CFD investigations and comparison with experimental results

A computational fluid dynamic (CFD) model for the pressure vessel of the evolutionary pressurized reactor (EPR™) was developed and validated. The aim of this model is the simulation of transients where three-dimensional effects play a strong role, such as boron dilution and main steam line break (MSLB) scenarios. First, a full solid (CAD) model has been built, that includes all details of the reactor pressure vessel (RPV) and the internals which are important for fluid dynamic analyses. The solid model has then been used as basis for the generation of the computational mesh necessary to carry out CFD simulations. Both a hexahedral and a polyhedral mesh have been created. The CFD model has been validated against experimental results of the JULIETTE facility, a 1:5 scaled mock-up of the EPR™ reactor RPV built by AREVA and equipped with advanced instrumentation.The performances of the hexahedral and the polyhedral meshes are investigated in relation to the agreement with experimental data, convergence and CPU requirements. In addition, the effect of the cold-leg swirls on the velocity field inside the RPV is investigated. These swirls mimic the effects of the main coolant recirculation pumps on the flow field at the entrance of the RPV. It is shown that the CFD model is able to capture the shift of the maximum velocity in the downcomer annulus observed in the experimental results. Good qualitative as well as quantitative agreement with the experimental data is achieved.     

Fusion-neutron production in the TFTR with Deuterium neutral-beam injection

We report measurements of the fusion reaction rate in the Tokamak Fusion Test Reactor (TFTR) covering a wide range of plasma conditions and injected neutral-beam powers up to 6.3 MW. The fusion neutron production rate in beam-injected plasmas decreases slightly with increasing plasma density n_e, even though the energy confinement parameter n_eE generally increases with density. The measurements indicate and Fokker-Planck simulations show that with increasing density the source of fusion neutrons evolves from mainly beam-beam and beam-target reactions at very low n_e to a combination of beam-target and thermonuclear reactions at high n_e. At a given plasma current, the reduction in neutron source strength at higher n_e is due to both a decrease in electron temperature and in beam-beam reaction rate. The Fokker-Planck simulations also show that at low n_e, plasma rotation can appreciably reduce the beam-target reaction rate for experiments with coinjection only. The variation of neutron source strength with plasma and beam parameters is as expected for beam-dominated regimes. However, the Fokker-Planck simulations systematically overestimate the measured source strength by a factor of 2–3; the source of this discrepancy has not yet been identified.On leave from RCA David Sarnoff Research Center, Princeton, New Jersey 08540.On assignment from Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831.On leave from Idaho National Engineering Laboratory, EG&G Idaho, Inc., Idaho Falls, Idaho 83415.     

Experimental studies on steel corrosion in Pb-Bi with steam injection

Experimental studies on steel corrosion were performed in simulated PBWFR (Pb-Bi cooled direct contact boiling water fast reactor) coolant environment. Some candidate steels of high Cr contents were immersed in steam-injected liquid Pb-Bi pool to investigate how their Cr contents and oxygen potential in Pb-Bi or (P_H2/P_H2O) in the steam influence their corrosion behaviors at temperature range of the reactor operation. Test specimens were made from eight types of steel with Cr contents ranged from 8 to 18%. The experiments were conducted by exposing these specimens to Pb-Bi pool where steam was injected. (P_H2/P_H2O) ratios of the steam were employed as experimental parameter, ranged from < 3×10⁻⁷ to 1×10⁻⁵ to control oxygen potential of Pb-Bi. Exposure temperatures were studied of 400, 450 and 500°C. It was found that 12Cr steel (HCM12/HCM12A) was the most resistant to corrosion and therefore a candidate reactor material.     

Sloshing effect on the dynamic behavior of horizontal cylindrical shells

The present study investigates the effect of free surface motion of a fluid on the dynamic behavior of thin-walled cylindrical shells. This paper outlines a semi-analytical approach to dynamic analysis of a fluid-filled horizontal cylindrical shell taking into account free surface motion; sloshing. The aim of the method is to provide a general approach that can be used for both analysis and synthesis of fluid/structure interaction problems in horizontal cylindrical shells focusing on the dynamic interaction between a flexible structure and incompressible and inviscid flow. The approach is very general; it allows dynamic analysis of both uniform and non-uniform cylindrical shells and considers the fluid forces and includes the sloshing effect exerted on the structure. The hybrid method developed in this work incorporates a combination of the classic finite element approach and thin shell theory to determine the specific displacement functions. Mass and stiffness matrices of the shell are determined by precise analytical integration. A potential function is applied to develop the dynamic pressure due to the fluid. The kinetic and potential energies are evaluated for a range of fluid heights to find the influence of the fluid on the dynamic responses of the structure. The influence of physical and geometrical parameters on the fluid-structure system has been considered in the numerical solutions. When these results are compared with corresponding results available in the literature, both theoretical and experimental, very good agreement is obtained.     

蒙特卡罗模拟研究水平井密度测井中岩屑层的影响

利用蒙特卡罗方法,分别通过改变地层模型的岩性和水平井筒模型内岩屑层的厚度,研究了在多种地层中,水平井筒内0-5cm厚的岩屑层对密度测量的影响.为了保证模拟结果的可靠性,把模拟结果与前人实验数据进行了基准校正.研究表明,厚度在2cm以内的岩屑层对密度测量的影响是稳定的,可以用脊肋图的方式进行补偿校正,而岩屑层厚度大于2 cm之后,其对密度测量的影响不再容易校正.针对DSDL-8723双源距密度测井仪,初步给出了水平井中岩屑层对孔隙度影响的校正图版和公式.