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Bia So 1-4 Chuan Kich Thuoc. So 4.2019 ISSN 1810-5408 Nuclear Science and Technology Volume 9, Number 4, December 2019 Published by VIETNAM ATOMIC ENERGY SOCIETY VIETNAM ATOMIC ENERGY INSTITUTE NUCLEAR SCIENCE AND TECHNOLOGY Volume 9, Number 4, December 2019 Editorial Board Editor-in-chief Tran Huu Phat (VINATOM) Executive Editors Vuong Huu Tan (VARANS) Tran Chi Thanh (VINATOM) Cao Dinh Thanh (VINATOM) Hoang Anh Tuan (VAEA) Editors Nguyen Kien Cuong (VINATOM) Le Hong Khiem (IOP) Nguyen Nhi Dien (VINATOM) Dao Tien Khoa (VINATOM) Nguyen Thi Kim Dung (VINATOM) Tran Hoai Nam (Duy Tan University) Ho Manh Dung (VINATOM) Dang Duc Nhan (VINATOM) Nguyen Nam Giang (VINATOM) Nguyen Hao Quang (VINATOM) Trinh Van Giap (VINATOM) Nguyen Mong Sinh (VINATOM) Le Ngoc Ha (108 Military Central Hospital) Tran Duc Thiep (IOP) Phan Son Hai (VINATOM) Dang Quang Thieu (VINATOM) Le Huy Ham (VAAS) Le Ba Thuan (VINATOM) Nguyen Quoc Hien (VINATOM) Nguyen Trung Tinh (VARANS) Le Van Hong (VINATOM) Tran Ngoc Toan (VINATOM) Nguyen Tuan Khai (VINATOM) Duong Thanh Tung (VARANS) Pham Dinh Khang (VINATOM) Nguyen Nu Hoai Vi (VARANS) Science Secretary Hoang Sy Than (VINATOM) .................................................................................................................................................................................................................... Copyright: ©2008 by the Vietnam Atomic Energy Society (VAES), Vietnam Atomic Energy Institute (VINATOM). Pusblished by Vietnam Atomic Energy Society, 59 Ly Thuong Kiet, Hanoi, Vietnam Tel: 84-24-39420463 Fax: 84-24-39424133 Email: [email protected] Vietnam Atomic Energy Institute, 59 Ly Thuong Kiet, Hanoi, Vietnam Tel: 84-24-39420463 Fax: 84-24-39422625 Email: [email protected] .................................................................................................................................................................................................................... Contents Bubble behavior in liquid-gas two-phase flow behind a cross-shaped obstacle in a vertical circular duct K. Takase, G. Kawasaki, K. Ueta……………………………………………..………………. 01 Evaluation of the Potential for Containment Bypass due to Steam Generator Tube Rupture in VVER-1000/V320 Reactor during Extended SBO sequence using SCDAP/RELAP5 code Nguyen Van Thai, Doan Manh Long, Tran Chi Thanh …………………………………… 09 Study on transmutation efficiency of the VVER-1000 fuel assembly with different minor actinide compositions Tran Vinh Thanh, Vu Thanh Mai, Hoang Van Khanh, Pham Nhu Viet Ha ……………. 18 Determination of in situ detection efficiency for IM-NAA of non-standard geometrical samples Nguyen Duy Quang, Trinh Van Cuong, Tran Tuan Anh, Ho Van Doanh, Nguyen Thi Tho, Ho Manh Dung……………………………………………………………………………. 27 Evaluating uncertainty of some radiation measurand using Monte Carlo method Bui Duc Ky, Nguyen Ngoc Quynh, Duong Duc Thang, Le Ngoc Thiem, Ho Quang Tuan, Tran Thanh Ha, Bui Thi Anh Duong, Nguyen Huu Quyet, Duong Van Trieu...... 34 Evaluation of image reconstruction algorithms in cone-beam computed tomography technique Tran Thuy Duong, Bui Ngoc Ha…………………………………………………………….. 41 Relative output factors of different collimation systems in truebeam STx medical linear accelerator Do Duc Chi, Tran Ngoc Toan, Robin Hill, Nguyen Do Kien …………………………….. 48 Nuclear Science and Technology, Vol.9, No. 4 (2019), pp. 01-08 Bubble behavior in liquid-gas two-phase flow behind a cross-shaped obstacle in a vertical circular duct K. Takase*, G. Kawasaki, K. Ueta *Department of Nuclear System Safety Engineering, Nagaoka University of Technology, Japan E-mail: [email protected] (Received 07 November 2019, accepted 26 December 2019) Abstract: Grid spacers installed in subchannels of fuel assemblies for nuclear reactors can promote heat transfer. However, the fluid velocity and bubble behavior are greatly affected as the cross- sectional area of the flow passage changes. Therefore, the void fraction distribution behind the obstacle that simulates the grid spacer shape simply was measured by using a wire mesh sensor (WMS) system. Moreover, a two-phase flow analysis was performed to investigate the effect of the obstacle on the bubble behavior in a vertical duct. Keywords: Bubbler, Two-phase flow, Obstacle, Vertical duct, WMS, Experiment, Analysis. I. INTRODUCTION simulated spacer was visually observed and the void fraction and interfacial velocity Clarifying two-phase characteristics distributions just behind the simulated in a nuclear reactor core is important in spacer was measured. particular to enhance the thermo-fluid safety of nuclear reactors. Moreover, correct data II. EXPERIMENTAL METHOD on bubbly flow in subchannels with spacers are needed in order to verify two-phase flow 1. Experimental Apparatus models in conventional nuclear safety The experimental apparatus mainly analysis codes and validate predicted data consists of a measuring section and by current CFD codes like a direct two- water/air supply lines and is shown in Fig. phase flow analysis code (Douce, et al., 1. The measuring section includes a vertical 2010). Spacers installed in subchannels of flow channel with a diameter of 58 mm fuel assemblies have the role of keeping the made of an acrylic resin, inlet and outlet interval between adjacent fuel rods constant. plenums, and an air injection nozzle with Similarly, in case of PWR the spacer has 120 injection holes with a diameter of 0.6 also the role as the turbulence promoter. mm. Water flows through the inlet plenum When the transient event occurs in a nuclear reactor, two-phase flow is generated by into the flow channel and goes up through boiling of water due to heating of fuel rods. the measuring section to the outlet plenum. Therefore, it is important to confirm the Air is supplied from the air injection nozzle Fig. 2 Observed into the flow channel. As a result, water is rising bubbles in a bubbly flow behavior around the spacer. flow channel The purpose of this study is to make the mixed with air and then a water-air two- effect of the spacer affecting the bubbly phase flow is formed as can be seen in Fig. flow clear and obtain code validation data. 2. Bubbly flow conditions are determined So bubble dynamics around the simply by both flow rates of water and air. ©2019 Vietnam Atomic Energy Society and Vietnam Atomic Energy Institute BUBBLE BEHAVIOR IN LIQUID-GAS TWO-PHASE FLOW BEHIND A CROSS-SHAPED… f58 mm Wire mesh Sensor Cross- direction Flow shaped obstacle 2600 mm 2600 High speed Camera 1150 mm 1150 20 mm or 100 mm 100 or mm 20 Air nozzle Fig. 1. Outline of an experimental apparatus Fig. 2. Observed rising bubbles in a flow channel 2. Wire-Mesh Sensor System temperatures of water and air are measured at the water/air supply piping lines. The void fraction distribution at the horizontal cross- section in the flow channel is The WMS can obtain the void fraction measured with a wire-mesh sensor (WMS) distribution in a cross-section of the flow channel system (Prasser et al., 1998; 2000; 2001). by measuring the electric current from the Complicated behavior of an interface between transmitter-side wire layer through the fluid to the water and air of each bubble is visually receiver-side wire layer. Both wire layers consist observed with a high speed camera (HSC). of nine wires respectively and are installed in the Moreover, two-phase pressure loss is measured flow channel with the distance of 3 mm in the with seven differential pressure transducers flow direction. The wire diameter is 0.3 mm. installed in the arbitrary locations in the Appearance and measuring wires of the WMS vertical direction of the flow channel. In are shown in Fig. 3. A mearing method with addition, both flow rates, pressures and the WMS is as follows. Layout of each wire of transmitter and Clipped layout of Appearance of a wire-mesh sensor receiver in the vertical direction each wire (Dimension: mm) in the horizontal Fig. 3. Appearance and layout directionof a wire -mesh sensor in a circular flow channel 2 K. TAKASE et al. 1) Current is given to the transmitter-side Moreover, the cross-correlation wire layer; coefficient used to obtain the interfacial velocity is obtained from the relationship 2) The current flows from the transmitter- between both data measured by a couple of side wire layer through the fluid to the the WMS layers and is expressed by the receiver-side wire layer; following equation. 3) The voltage is measured at the location where each wire intersects; and, n xtt x y y 4) Void fraction between both wires cor() t1 (3) n is obtained. 22 xtt x y y The following equation is used for t1 the conversion from the voltage to the Here, x and y represent time series void void fraction. fraction data measured with the WMS UU installed upstream in the flow direction and L i, j (1) ij, the WMS installed downward. The n shows UULG the number of comparison data. The cross- Here, is the local void fraction, (i, j) correlation coefficient, cor() has the value is the position where two wires intersect in from -1 to 1, and it shows 1 when both data of the cross-section of the flow channel, U [V] x and y have the positive correlation, -1 when is the voltage measured by the WMS at two- those are the negative correlation, and 0 when phase flow condition, Each of UL [V] and those have no correlation. UG [V] is the voltage measured by the WMS at the single-phase flow condition of liquid or gas. On the other hand, gas-liquid interface velocity is determined using the time-series void fraction data measured by a couple of the WMS layers which are installed upstream and downstream of the flow channel. Two void fraction data by both WMS layers are compared. In Fig 4, time difference, , in case that the cross-correlation coefficient between both void fraction data shows the highest match is identified. Finally, the gas-liquid interface velocity, ub, is calculated by Eq. (2) using S and . Here, S is the distance between both receiver-side wire layers. S u (2) Fig. 4. Example of time variation of void fraction b data at the different vertical positions 3 BUBBLE BEHAVIOR IN LIQUID-GAS TWO-PHASE FLOW BEHIND A CROSS-SHAPED… 3.
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