A Comparison of the Corrosion Resistance of Iron-Based Amorphous Metals and Austenitic Alloys in Synthetic Brines at Elevated Temperature - Possible New Material for Spent Nuclear Fuel Storage

ABSTRACTSpent nuclear fuel contains fissionable materials (235U, 239Pu, 241Pu, etc.). To prevent nuclear criticality in spent fuel storage, transportation, and during disposal, neutron-absorbing materials (or neutron poisons, such as borated stainless steel, Boral™, Metamic™, Ni-Gd, and others) would have to be applied. The success in demonstrating that the High-Performance Corrosion-Resistant Material (HPCRM) can be thermally applied as coating onto base metal to provide for corrosion resistance for many naval applications raises the interest in applying the HPCRM to USDOE/OCRWM spent fuel management program. The fact that the HPCRM relies on the high content of boron to make the material amorphous – an essential property for corrosion resistance – and that the boron has to be homogenously distributed in the HPCRM qualify the material to be a neutron poison.

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The use of long-span coating plates in case of reconstruction of “wet” spent nuclear fuel storage facilities

IOP Conference Series Materials Science and Engineering ◽

10.1088/1757-899x/962/2/022064 ◽

2020 ◽

Vol 962 ◽

pp. 022064

Author(s):

T Belash ◽

S Travin

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Long Span ◽

Fuel Storage ◽

Storage Facilities

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

Nuclear Technology ◽

10.13182/nt06-a3752 ◽

2006 ◽

Vol 155 (2) ◽

pp. 133-148 ◽

Cited By ~ 5

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

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Prediction of the maximum temperature inside container with spent nuclear fuel

Nuclear and Radiation Safety ◽

10.32918/nrs.2018.2(78).05 ◽

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.

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