Hidden disbond detection in spent nuclear fuel storage systems using air-coupled ultrasonics

2016 ◽  
Author(s):  
Homin Song ◽  
John S. Popovics
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Storage Systems ◽  
Fuel Storage ◽  
Disbond Detection ◽  
Air Coupled Ultrasonics

scholarly journals COMPARATIVE ANALYSIS OF NUMERICAL METHODS USED FOR THERMAL MODELING OF SPENT NUCLEAR FUEL DRY STORAGE SYSTEMS

2019 ◽  
pp. 75-79
Author(s):  
S. Alyokhina ◽  
Y. Matsevity ◽  
V. Dudkin ◽  
R. Poskas ◽  
A. Sirvydas ◽  
...  
Keyword(s):  
Comparative Analysis ◽  
Nuclear Fuel ◽  
Nuclear Energy ◽  
Storage Time ◽  
Spent Nuclear Fuel ◽  
Storage Systems ◽  
Storage Technology ◽  
Dry Storage ◽  
Fuel Storage ◽  
Interim Storage

Management of spent nuclear fuel is a very important part in the whole cycle of nuclear energy generation. Usually “dry” storage technology in casks is selected for the interim storage of spent nuclear fuel for up to 50 years after pre-storage time in water pools. In this paper, two case studies were carried out to highlight the differences and similarities between Ukraine and Lithuania in spent nuclear fuel storage.

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.

Burnup Credit in the Criticality Safety Analysis of Spent Fuel in Storage Systems

2014 ◽  
Author(s):  
Vladyslav Soloviov
Keyword(s):  
Isotopic Composition ◽  
Nuclear Fuel ◽  
Beta Decay ◽  
Spent Nuclear Fuel ◽  
Storage Systems ◽  
Multiplication Factor ◽  
Spent Fuel ◽  
Neutron Multiplication ◽  
Initial Fuel ◽  
Effective Neutron

In this paper accounting of spent nuclear fuel (SNF) burnup of RBMK-1000 with actinides and full isotopic composition has been performed. The following characteristics were analyzed: initial fuel enrichment, burnup fraction, axial burnup profile in the fuel assembly (FA) and fuel weight. As the results show, in the first 400 hours after stopping the reactor, there is an increase in the effective neutron multiplication factor (keff) due to beta decay of 239Np into 239Pu. Further, from 5 to 50 years, there is a decrease in keff due to beta decay of 241Pu into 241Am. Beyond 50 years there is a slight change in the criticality of the system. Accounting for nuclear fuel burnup in the justification of nuclear safety of SNF systems will provide an opportunity to increase the volume of loaded fuel and thus significantly reduce technology costs of handling of SNF.

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

Burnup Credit in the Criticality Safety Analysis of Spent Fuel in Transportation and Storage Systems

2013 ◽  
Author(s):  
Vladyslav Soloviov
Keyword(s):  
Nuclear Fuel ◽  
Beta Decay ◽  
Spent Nuclear Fuel ◽  
Storage Systems ◽  
Multiplication Factor ◽  
Spent Fuel ◽  
Neutron Multiplication ◽  
Initial Fuel ◽  
Effective Neutron ◽  
And Storage

In this paper accounting of spent nuclear fuel (SNF) burnup of RBMK-1000 only with actinides has been performed. The following characteristics were analyzed: initial fuel enrichment, burnup fraction, axial burnup profile in the fuel assembly (FA) and fuel weight. As the results show, in the first 400 hours after stopping the reactor, there is an increase in the effective neutron multiplication factor (keff) due to beta decay of 239Np into 239Pu. Further, from 5 to 50 years, there is a decrease in keff due to beta decay of 241Pu into 241Am. Beyond 50 years there is a slight change in the criticality of the system. Accounting for nuclear fuel burnup in the justification of nuclear safety of SNF systems will provide an opportunity to increase the volume of loaded fuel and thus significantly reduce technology costs of handling of SNF.

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
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