Development and Testing of an Advanced Neutron-Absorbing Gadolinium Alloy for Spent Nuclear Fuel Storage

2006 ◽  
Vol 155 (2) ◽  
pp. 133-148 ◽  
Author(s):  
Ronald E. Mizia ◽  
Tedd E. Lister ◽  
Patrick J. Pinhero ◽  
Tammy L. Trowbridge ◽  
William L. Hurt ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Storage

scholarly journals Prediction of the maximum temperature inside container with spent nuclear fuel

2018 ◽  
pp. 31-35
Author(s):  
S. Alyokhina ◽  
О. Dybach ◽  
A. Kostikov ◽  
D. Dimitriieva
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Maximum Temperature ◽  
Storage Facility ◽  
Storage Container ◽  
Atmospheric Air ◽  
Decay Heat ◽  
Fuel Storage ◽  
Maximum Temperatures ◽  
Cooling Air

The definition of the thermal state of containers with spent nuclear fuel is important part of the ensuring of its safe storage during all period of storage facility operation. The this work all investigations are carried out for the storage containers of spent nuclear fuel of WWER-1000 reactors, which are operated in the Dry Spent Nuclear Fuel Storage Facility in Zaporizhska NPP. The analysis of existing investigations in the world nuclear engineering science concerning to the prediction of maximum temperatures in spent nuclear fuel storage container is carried out. The absence of studies in this field is detected and the necessity of the dependence for the maximum temperature in the storage container and temperature of cooling air on the exit of ventilation duct from variated temperatures of atmospheric air and decay heat formulation is pointed out. With usage of numerical simulation by solving of the conjugate heat transfer problems, the dependence of maximum temperatures in storage container with spent nuclear fuel from atmospheric temperature and decay heat is detected. The verification of used calculation method by comparison of measured air temperature on exit of ventilation channels and calculated temperature of cooling air was carried out. By regression analysis of numerical results of studies the dependence of ventilation air temperature from the temperature of atmospheric air and the decay heat of spent nuclear fuel was formulated. For the obtained dependence the statistical analysis was carried out and confidence interval with 95% of confidence is calculated. The obtained dependences are expediently to use under maximum temperature level estimation at specified operation conditions of spent nuclear fuel storage containers and for the control of correctness of thermal monitoring system work.

A Method of Performing Shutdown Reactivity Measurements in Spent Nuclear Fuel Storage Pools

1981 ◽  
Vol 52 (3) ◽  
pp. 347-353 ◽  
Author(s):  
Samuel H. Levine ◽  
Mortimer A. Schultz ◽  
Daren Chang
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Storage ◽  
Storage Pools

Radiation induced corrosion of copper for spent nuclear fuel storage

2013 ◽  
Vol 92 ◽  
pp. 80-86 ◽  
Author(s):  
Åsa Björkbacka ◽  
Saman Hosseinpour ◽  
Magnus Johnson ◽  
Christofer Leygraf ◽  
Mats Jonsson
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Fuel Storage ◽  
Radiation Induced

scholarly journals Skyshine Calculations for a Large Spent Nuclear Fuel Storage Facility with SCALE 6.2.3

2021 ◽  
pp. 1-16
Author(s):  
Georgeta Radulescu ◽  
Kaushik Banerjee ◽  
Thomas M. Miller ◽  
Douglas E. Peplow
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Storage Facility ◽  
Fuel Storage

Rationalization of Radiation Shielding Design for Spent Nuclear Fuel Storage Building

2008 ◽  
Author(s):  
Yuji Nemoto ◽  
Toshihisa Tsukiyama ◽  
Shigeki Nemezawa ◽  
Hideo Nakano
Keyword(s):  
Nuclear Fuel ◽  
Seismic Design ◽  
Scattered Radiation ◽  
Spent Nuclear Fuel ◽  
Heat Removal ◽  
Radiation Shielding ◽  
Air Supply ◽  
Exhaust Duct ◽  
Fuel Storage ◽  
Shielding Design

A spent nuclear fuel storage building is generally a structure provided with heat removal, radiation shielding functions, and a seismic design. The facility has air supply ducts and a chimney exhaust duct for removing heat through natural cooling, with the structural shapes determined by the demands of the above functions. In radiation protection design, radiation levels must be kept below acceptable levels for the general public. The radiation dose can be lowered by increasing the concrete thickness, as typically applied in radiation shielding design, or by increasing the distance. The setting of additional shielding plates also helps reduce the scattered radiation escaping from the air supply and exhaust ducts. However, such protective structures against the scattered radiation challenges in effective heat removal and seismic design. Therefore, determining a building structure that can satisfy all safety demands requires a great deal of time. This study aims to effectively achieve radiation shielding. The height and width of the exhaust duct were considered, and the correlation of these parameters was studied. In the calculation, two-dimensional Sn code (DORT) was used to examine the validity of the results. Monte Carlo N-Particle Transport Code (MCNP) calculations were also made for comparison with the DORT results. The cross-section libraries of JENDL3.3 and DLC23F were used in this calculation, with the difference being clarified.

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