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| 1 | Cascading dam breach process simulation using a coupled modeling platform显示文摘This study evaluates the possibility of a cascade failure by developing a coupled breach-modeling platform based on onedimensional flow modeling of the river channel, flood propagation, regulation process of reservoir fluctuation, overtopping with breaching, and wave damping downstream. A hyperbolic model of the DB-IWHR was embedded into the platform to simulate the dam breaching process. Five breach models and software were used to calculate the Tangjiashan barrier lake breaching. The results of a sensitivity study were then compared with the measured data. The peak flow and the time of occurrence were confirmed to be predictable with a reasonable accuracy if the input values were within ranges appropriate for the model. The approach was applied to a case involving two layout planning schemes for a cascade of rock-filled dams under extreme operating conditions. The probability of the failure of a key control cascade downstream caused by a continuous cascade breach upstream was simulated. Moreover, measures to prevent the transmission of risk by advance warnings were investigated. The proposed methodology and the discharge capacity measures provide guidelines to assess the risk to a cascade of dams under extreme operating conditions and offer support for the design criteria of unusual discharge structures for very large dams. | LIU ZhiPing GUO XinLei ZHOU XingBo FU Hui XIA QingFu LI ShaoJun | 2019 | Science China(Technological Sciences)2019，62，8： | 1 |
| 2 | Design of Annular Fuel Zero Power Physics Experiment Reactor显示文摘The zero-power physics experiment reactor of annular fuel is a vertical small-scale multifunctional reactor,which uses light water as a moderator and a reflection layer,and cadmium as a safety rod to adjust rod materials.The threedimensional structure of the reactor is shown in Fig.1. | ZHANG Geng XIA Zhaodong ZHOU Qi LI Hang PAN Cuijie LIANG Shuhong ZHU Qingfu | 2017 | Annual Report of China Institute of Atomic Energy2017，，1： | 0 |
| 3 | Physical Design of Key Critical Experimental Device in Post-treatment Plant显示文摘In order to study the multi-body criticality safety problem of the post-treatment plant,the existing critical safety analysis software was used to analyze the applicability of the problem,and a multi-body critical experimental device for uranyl nitrate solution(uranium solution)was designed.Aiming at suiting two different enrichment of uranium nitrate,a critical experimental device compatible with the loading of two kinds of nuclear materials was designed by rationally planning the concentration of uranium solution and the value of control rod. | CHENG Yuting XIA Zhaodong ZHU Qingfu ZHOU Qi | 2018 | 中国原子能科学研究院年报2018，，1： | 0 |
| 4 | Annular Fuel Zero Power Physics Critical Experiment显示文摘Annular fuel is a new type of fuel that passes through both coolants inside and outside.It has many advantages in terms of economy and safety compared with traditional solid fuels.The structure is shown in Fig.1.Since the structure of the solid fuel cell,the core physical calculation analysis method is different from the traditional solid fuel cell.Before this,there is no critical fuel core critical experimental data at home and abroad,resulting in the physical design of the annular fuel cores carried out at this stage relies on the program-to-program method to verify each other,without effective reliability verification. | ZHANG Geng XIA Zhaodong ZHOU Qi ZHU Qingfu | 2018 | 中国原子能科学研究院年报2018，，1： | 0 |
| 5 | Verification of Reactor Core Physical Analysis Code for Annular Fuel显示文摘In order to meet that computational requirements of the physical performance study of the annular fuel core,a annular fuel calculation module is added to the PWR fuel management package,because there is no application of the annular fuel engineering at present,the accuracy of the calculation cannot be verified by the experimental data,therefore,the Monte Carlo calculation program MVP-BURN was used as the benchmark to verify the annular fuel.The program verification is mainly divided into two parts:the first part takes the Qinshan PhaseⅡreactor as an example,and the natural deviation between the CMS and the MVP-BURN is obtained by comparing the calculation results of the fuel pin and the assembly,and the calculation results are as shown in Fig.1.For solid fuel pin and assembly,the maximum deviation of the two programs is 0.005; | PAN Cuijie XIA Zhaodong ZHU Qingfu | 2018 | 中国原子能科学研究院年报2018，，1： | 0 |
| 6 | Research on Installation and Setting of CAAS显示文摘The criticality accident alarm system(CAAS)is used to monitor the absorbed dose in the places where there is a critical accident risk.When a criticality accident occurs,the alarm will be quickly triggered and the nuclear emergency response will be initiated.However,the research in this field has not been carried out interiorly,and of which there is a lack of references.For this reason,the Nuclear Critical Safety Center undertakes works to solve the problem of location installation and alarm threshold setting of CAAS. | LIU Feng ZHU Qingfu XIA Zhaodong ZHOU Qi | 2018 | 中国原子能科学研究院年报2018，，1： | 0 |
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