A new design concept and seismic margin assessment for a spent fuel storage system

2018 ◽  
Vol 326 ◽  
pp. 150-161 ◽  
Author(s):  
Jinho Oh ◽  
Shinyoung Kwag ◽  
Jongmin Lee
Author(s):  
Jinhua Wang ◽  
Bing Wang ◽  
Bin Wu ◽  
Yue Li

There are more than 400 reactors in operation to generate electricity in the world, most of them are pressurized water reactors and boiling water reactors, which generate great amount of spent fuel every year. The residual heat power of the spent fuel just discharged from the reactor core is high, it is required to store the spent fuel in the spent fuel storage pool at the first 5 years after discharged from the reactor, and then the spent fuel could be moved to the interim storage facility for long term storage, or be moved to the factory for final treatment. In the accident of the Fukushima in 2011, the spent fuel pool ruptured, which led to the loss of coolant accident, it was very danger to the spent fuel assemblies stored in the pool. On the other hand, the spent fuel stored in the dry storage facility was safe in the whole process of earthquake and tsunami, which proved inherent safety of the spent fuel dry storage facility. In china, the High Temperature gas cooled Reactor (HTR) is developing for a long time in support of the government. At the first stage, HTR-10 with 10MW thermal power was designed and constructed in the Institute of Nuclear Energy Technology (INET) of Tsinghua University, and then the High Temperature Reactor-Pebble bed Modules (HTR-PM) is designed to meet the commercial application, which is in constructing process in Shandong Province. HTR has some features of the generation four nuclear power plant, including inherent safety, avoiding nuclear proliferation, could generate high temperature industrial heat, and so on. Spherical fuel elements would be used as fuel in HTR-PM, there are many coating fuel particles separated in the fuel element. As the fuel is different for the HTR and the PWR, the fuel element would be discharged into the appropriate spent fuel canister, and the canister would be stored in the appropriate interim storage facility. As the residual power density is very low for the spent fuel of HTR, the spent fuel canister could be cooled with air ventilation without water cooling process. The advantage of air cooling mode is that it is no need to consider the residual heat removal depravation due to loss of coolant accident, so as to increase the inherent safety of the spent fuel storage system. This paper introduced the design, arrangement and safety characteristics of the spent fuel storage well of HTR-PM. The spent fuel storage wells have enough capacity to hold the total spent fuel canisters for the HTR-PM. The spent fuel storage facility includes several storage wells, cold intake cabin, hot air discharge cabin, heat shield cylinders, well lids and so on. The cold intake cabin links the inlets of all the wells, which would be used to import cold air to every well. The hot air discharge cabin links the outlets of all the wells, which would be used to gather heated air discharged from every well, the heated air would be discharged to the atmosphere through the ventilating pipe at the top of the hot air cabin. The design of the spent fuel storage well and the ventilating pipe could discharge the residual heat of the spent fuel canisters in the storage wells, which could ensure the operating safety of the spent fuel storage system.


2009 ◽  
Vol 239 (3) ◽  
pp. 551-558 ◽  
Author(s):  
J.C. Lee ◽  
W.S. Choi ◽  
K.S. Bang ◽  
K.S. Seo ◽  
S.Y. Yoo

Author(s):  
Bin Wu ◽  
Jinhua Wang ◽  
Yue Li ◽  
Jiguo Liu

In the spent fuel storage system of pebble-bed high temperature gas-cooled reactor, several air cylinders would be employed in complex machines, such as the spent fuel charging apparatus and the spent fuel canister crane. The cylinders were designed to actuate movements smoothly in radioactive environment. In order to lock them in safe position when the compressed air source is offline by accident, an electromagnetic self-locking device was designed. When power-off, the compressive spring would push out the lock plunger to enable self-lock. When power-on, the lock plunger would be withdrawn by the magnetic force of the coil to unlock the cylinder. In order to optimize the design more efficiently, numerical simulation was performed to optimize geometry parameters of the structure surrounding the working air gap so as to improve the performance of the device. A prototype was then fabricated. Combining the simulation results with experimental test, the actuating force characteristics of the device in locking and unlocking process was analyzed. The temperature rise when the device stays unlocked with power supply was also calculated and validated. The results showed that this electromagnetic self-locking device could realize the locking and unlocking functions effectively, and the maximum temperature rise also conforms the required limit. The as-fabricated device would help guarantee the fail-safe feature of the air cylinders of complex machines in compressed air outage.


1990 ◽  
Author(s):  
L.A. Strope ◽  
M.A. McKinnon ◽  
D.J. Dyksterhouse ◽  
J.C. McLean

Author(s):  
Donald W. Lewis

U. S. commercial reactor plants are installing spent fuel storage facilities formally called Independent Spent Fuel Storage Installations (ISFSI) to provide needed storage space for spent nuclear fuel assemblies. Although this might be a primary objective for the utility that owns the plant, the U.S. Nuclear Regulatory Commission (U.S. NRC) has other priorities as addressed by ISFSI regulations in Title 10 of the Code of Federal Regulations, Part 72. These regulations establish a number of criteria that ensure that above all, the storage of spent nuclear fuel does not adversely affect the health and safety of the public or the environment. There are 3 primary ISFSI design activities that ensure the health and safety of the public and protection of the environment: site selection, storage system selection, and storage facility design. The regulatory requirements that address ISFSI site selection are found in 10 CFR 72, Subpart E, “Siting Evaluation Factors.” This section requires that potential ISFSI sites be assessed for impacts such as site characteristics that may affect safety or the environment, external natural and man-induced events, radiological and other environmental conditions, floodplains and natural phenomena, man-made facilities and activities that could endanger the ISFSI, and construction, operation, and decommission activities. All of these potential impacts must be carefully evaluated. First, the ISFSI capacity requirements should be determined. Potential sites should then be evaluated for siting impacts to ensure the site has adequate space, it can be licensed, it will minimize radiological doses to the general public and on-site workers, and construction, operation, and decommissioning won’t have a major effect on the environment or nearby population. The regulatory requirements that address storage system selection are found in 10 CFR 72, Subpart F, “General Design Criteria.” This section requires that the storage system be designed to withstand environmental conditions, natural phenomena, fires and explosions and that it includes confinement barriers, retrievability measures, and criticality safety. In order to be licensed by the U. S. NRC, all spent fuel storage systems must be evaluated to show how they meet these requirements. U.S. NRC approval of the system ensures that the requirements have been met and therefore ensure the health and safety of the public and environment are protected. The regulatory requirements that address the ISFSI design are also found in 10 CFR 72, Subpart F as well as 10 CFR 72, Subpart H, “Physical Protection.” Like the storage systems, the ISFSI site must be designed to withstand environmental conditions, natural phenomena, fires, and explosions. But the design must also include security provisions. Security features protect the spent fuel from attack or sabotage and therefore protect the health and safety of the public and the environment. The primary potential impact of spent fuel storage is radiation dose. The key regulatory requirement that addresses radiation dose is found in 10 CFR 72.104. This section requires that the dose to any individual member of the public not exceed 0.25 mSv (25 mrem) to the whole body, 0.75 mSv (75 mrem) to the thyroid, and 0.25 mSv (25 mrem) to any other organ, from exposure to direct radiation from the ISFSI, radioactive liquid or gaseous effluents, and radiation from other nearby nuclear facilities. Design features of the storage system and ISFSI include shielding by the cask enclosure, distance, berms as required, etc. to attenuate direct radiation, and confinement provisions to prevent radiological effluent leakage. The ISFSI must be located such that the cumulative doses from the ISFSI and reactor plant do not exceed regulatory requirements. Thus it can be seen that ISFSI site selection, storage system selection, and storage facility design all work together to ensure the health and safety of the public and environment are protected. Comments regarding the contents of this paper may be submitted to the author, Donald W. Lewis, Shaw Environmental & Infrastructure, 9201 E. Dry Creek Road, Centennial, Colorado, 80112, U.S.A.


Author(s):  
Daogang Lu ◽  
Yu Liu ◽  
Shu Zheng

Free standing spent fuel storage racks are submerged in water contained with spent fuel pool. During a postulated earthquake, the water surrounding the racks is accelerated and the so-called fluid-structure interaction (FSI) is significantly induced between water, racks and the pool walls[1]. The added mass is an important input parameter for the dynamic structural analysis of the spent fuel storage rack under earthquake[2]. The spent fuel storage rack is different even for the same vendors. Some rack are designed as the honeycomb construction, others are designed as the end-tube-connection construction. Therefore, the added mass for those racks have to be measured for the new rack’s design. More importantly, the added mass is influenced by the layout of the rack in the spent fuel pool. In this paper, an experiment is carried out to measure the added mass by free vibration test. The measured fluid force of the rack is analyzed by Fourier analysis to derive its vibration frequency. The added mass is then evaluated by the vibration frequency in the air and water. Moreover, a two dimensional CFD model of the spent fuel rack immersed in the water tank is built. The fluid force is obtained by a transient analysis with the help of dynamics mesh method.


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