The Criticality Safety Analysis of the Spent Fuel Storage Pool Area I in Small Modular Reactor

2014 ◽  
Vol 986-987 ◽  
pp. 589-592
Author(s):  
Xiang Zhen Han ◽  
Guo Shun You
Keyword(s):  
Geometric Model ◽  
Spent Fuel ◽  
Storage Pool ◽  
Small Modular Reactor ◽  
Accident Condition ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Spent Fuel Pool ◽  
Storage Racks ◽  
Pool Area

Based on the Monte Carlo calculation method, geometric model of spent fuel storage pool Area I of small modular reactor is established, assuming infinite 6×6 type storage racks. Calculation results show that the reactivity is maximal when the water density is 1.0g/cm3. The value of keff is 0.8729 in normal storage condition. The spacing of storage racks in spent fuel pool would change in an earthquake accident condition. The values of reactivity of spent fuel pool in the assumed earthquake accident condition are also calculated. The values of keff are between 0.872 and 0.876. Both in normal condition and assumed earthquake accident condition, the values of keff are less than 0.95, to meet nuclear safety regulatory requirements.

Development of Shearing Device for Reducing the Storage Volume of the Spent Fuel Associated Assemblies in Nuclear Power Plants

2017 ◽  
Author(s):  
Zhang Bin ◽  
Qiao Su-kai ◽  
Hao Qing-jun ◽  
Huang Hong-zhi ◽  
Ding Ming ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Storage Capacity ◽  
Spent Fuel ◽  
Storage Pool ◽  
Storage Volume ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Storage Racks

With the continuous running of the nuclear power plants, a great deal of unavailable spent fuel associated assemblies were and will be produced in the aggregates of the nuclear power plants, which are usually stored in the spent fuel storage pool and occupy lots of spent fuel storage racks, making the spent fuel storage facility of the nuclear power plants face the risk of being filled up. Therefore, it drives the nuclear power plants to seek a new method to increase the spent fuel storage capacity. In order to increase the storage capacity of the spent fuel storage racks, a shearing device is proposed to shear the rods and base plates (or spider assemblies) of the spent fuel associated assemblies, reducing the storage volume of the spent fuel associated assemblies and reducing the amount of the occupied spent fuel storage racks. The technology of water-hydraulic shear is applied to carry the shear process through underwater cold extrusion, effectively ensuring the integrity of the rod structure and avoiding the pollution caused by radioactive substances. Besides, no swarf would be produced to pollute the spent fuel storage pool. Through the finite element calculation and confirmation on the spot, it is verified that the bearing requirement of the fixed blade (the key assembly unit) of the shearing device is met during the relevant disassembling process. Currently, the shearing device has been successfully applied to reducing the storage volume of the spent fuel associated assemblies in LingAo Nuclear Power Plant. Therefore, the shearing device is of certain promoting and reference value.

Influence of Gap Size on Added Mass for Spent Fuel Storage Rack

2018 ◽  
Author(s):  
Daogang Lu ◽  
Yu Liu ◽  
Shu Zheng
Keyword(s):  
Vibration Frequency ◽  
Input Parameter ◽  
Added Mass ◽  
Water Tank ◽  
Spent Fuel ◽  
Free Standing ◽  
Fluid Force ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Spent Fuel Pool

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.

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

2021 ◽  
Author(s):  
Wen Yang ◽  
Xing Li ◽  
Jinrong Qiu ◽  
Lun Zhou
Keyword(s):  
Radiation Dose ◽  
Normal Condition ◽  
Radiation Safety ◽  
Spent Fuel ◽  
Dose Rates ◽  
Storage Pool ◽  
Transport Container ◽  
Photon Dose ◽  
Spent Fuel Storage ◽  
Fuel Storage

Abstract With the rapid development of nuclear energy, spent fuel will accumulate in large quantities. Spent fuel is generally cooled and placed in a storage pool, and then transported to a reprocessing plant at an appropriate time. Because spent fuel is content with a high level of radiation, spent fuel storage and transportation safety play important roles in the nuclear safety. Radiation dose safety are checked and validated using source analysis and Monte Carlo method to establish a radiation dose rate calculation model for PWR spent fuel storage pool and transport container. The calculation results show that the neutron and photon dose rates decrease exponentially with increase of water level under normal condition of storage pool. The attenuation multiples of neutron and photon dose rates are 4.64 and 1.59, respectively. According to radiation dose levels in different water height situations, spent fuel pool under loss of coolant accident can be divides into five workplaces. They are supervision zone, regular zone, intermittent zone, restricted zone and radiation zone. Under normal condition of transport container, the dose rates at the surface of the container and at a distance of 1 m from the surface are 0.1759 mSv/h and 0.0732 mSv/h, respectively. The dose rates decrease with the increasing radius of break accident, and dose rate at the surface of the transport container is 0.278 mSv/h when the break radius is 20 cm. Transport container conforms to the radiation safety standards of International Atomic Energy Agency (IAEA). This study can provide some reference for radiation safety analysis of spent fuel storage and transportation.

Criticality safety of the ET-RR-1 new spent fuel storage pool

2001 ◽  
Vol 28 (4) ◽  
pp. 375-383 ◽  
Author(s):  
E. Massoud ◽  
O.H. Sallam ◽  
E. Amin
Keyword(s):  
Spent Fuel ◽  
Storage Pool ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Criticality Safety
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