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

According to regulatory requirements, when carrying out handling operations with spent nuclear fuel (SNF), prevention of damage to the spent fuel assemblies (SFA) and especially fuel elements shall be ensured. For this purpose, it is necessary to exclude the risk of SFA falling, SFA uncontrolled displacements, prevent mechanical influences on SFA, at which their damage is possible. Special requirements for handling equipment (in particular, cranes) to exclude these dangerous events, the requirements for equipment strength, resistance to external impacts, reliability, equipment design solutions, manufacturing quality are analyzed in this work. The requirements of Ukrainian and U.S. regulatory documents also are considered. The implementation of these requirements is considered on the example of handling equipment, in particular, spent nuclear fuel storage facilities. This issue is important in view of creation of new SNF storage facilities in Ukraine. These facilities include the storage facility (SFSF) for SNF from water moderated power reactors (WWER): a Сentralized SFSF for storing SNF of Rivne, Khmelnitsky and South-Ukraine Nuclear Power Plants (СSFSF), and SFSF for SNF from high-power channel reactors (RBMK): a dry type SFSF at Chornobyl nuclear power plant (ISF-2). After commissioning of these storage facilities, all spent nuclear fuel from Ukrainian nuclear power plants will be placed for long-term “dry” storage. The safety of handling operations with SNF during its preparation for long-term storage is an important factor.

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

Nuclear Technology ◽

10.13182/nt81-a32709 ◽

1981 ◽

Vol 52 (3) ◽

pp. 347-353 ◽

Cited By ~ 1

Author(s):

Samuel H. Levine ◽

Mortimer A. Schultz ◽

Daren Chang

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Fuel Storage ◽

Storage Pools

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Experience With Damaged Spent Nuclear Fuel at U.S. DOE Facilities

Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management ◽

10.1115/icone14-89319 ◽

2006 ◽

Author(s):

Brett Carlsen ◽

Denzel Fillmore ◽

Roger L. McCormack ◽

Robert Sindelar ◽

Timothy Spieker ◽

...

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

National Laboratory ◽

Equipment Design ◽

Lessons Learned ◽

Nuclear Fuels ◽

Idaho National Laboratory ◽

Safe Storage ◽

And Storage ◽

Storage Facilities

This report summarizes some of the challenges encountered and solutions implemented to ensure safe storage and handling of damaged spent nuclear fuels (SNF). It includes a brief summary of some SNF storage environments and resulting SNF degradation, experience with handling and repackaging significantly degraded SNFs, and the associated lessons learned. This work provides useful insight and resolutions to many engineering challenges facing SNF handling and storage facilities. The context of this report is taken from a report produced at Idaho National Laboratory and further detailed information, such as equipment design and usage, can be found in the appendices to that report.

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