scholarly journals Verification of the GFLOW computer code using experimental data from the Maine Yankee spent-fuel storage pool. Final report

1983 ◽  
Author(s):  
R. Gay ◽  
D. Gloski
Keyword(s):  
Experimental Data ◽  
Computer Code ◽  
Final Report ◽  
Spent Fuel ◽  
Storage Pool ◽  
Spent Fuel Storage ◽  
Fuel Storage

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

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.

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