Preliminary Evaluation of Loading DOE Standardized Canisters in the CPP-603 Irradiated Fuel Storage Facility

2019 ◽  
Author(s):  
Daniel Albert Thomas
Keyword(s):  
Preliminary Evaluation ◽  
Storage Facility ◽  
Fuel Storage ◽  
Irradiated Fuel

Receipt and Storage Issues at the TMI-2 Irradiated Fuel Storage Installation

2002 ◽  
Author(s):  
Allan B. Christensen ◽  
Kenneth Custer ◽  
Rick Gardner ◽  
James Kaylor ◽  
James Stalnaker
Keyword(s):  
Hydrogen Generation ◽  
Reactor Fuel ◽  
Storage Facility ◽  
Spent Fuel ◽  
Dry Storage ◽  
Fuel Storage ◽  
Environmental Laboratory ◽  
Interim Storage ◽  
And Storage ◽  
Irradiated Fuel

In less than a year, up to 12 canisters of TMI-2 reactor fuel debris were loaded into each of 28 Dry Storage Containers (DSCs), and placed into interim storage at an Irradiated Spent Fuel Storage Facility (ISFSI) at the Idaho National Engineering and Environmental Laboratory (INEEL). Draining and drying the canisters, loading and welding the DSCs, shipping the DSCs 25 miles, and storing in the ISFSI initially required up to 3 weeks per DSC. Significant time efficiencies were achieved during the early stages, reducing the time to less than one week per DSC. These efficiencies were achieved mostly in canister draining and drying and DSC lid welding, and despite several occurrences that had to be resolved before continuing work. The ISFSI has been operated without issue since, with the exception that license basis monitoring has indicated an unusual pattern of season- and position-dependent hydrogen generation. This paper discusses some of the innovations and storage experiences for the first ISFSI designed for the storage of severely defected fuel.

Bulk Fuel Storage Facility Cape Canaveral Air Force Station, Florida. Environmental Assessment

2006 ◽  
Author(s):  
Larry W. Blackwell ◽  
Crystal M. Bailey ◽  
Susan Pearsall ◽  
Kyle A. Russell ◽  
Jeffery H. Scott
Keyword(s):  
Air Force ◽  
Environmental Assessment ◽  
Storage Facility ◽  
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.

Distributed Sensor System for Underground Fuel Storage Facility Monitoring and Leak Detection

2021 ◽  
Author(s):  
Matthew Nakamura ◽  
Noah Hafner ◽  
Joseph Brown
Keyword(s):  
Leak Detection ◽  
Sensor System ◽  
Storage Facility ◽  
Distributed Sensor ◽  
Fuel Storage

The Radiation Protection Design of PWR Spent Fuel Dry Storage Facility

2018 ◽  
Author(s):  
Liming Huang ◽  
Shouhai Yang ◽  
Jie Liu
Keyword(s):  
Radiation Protection ◽  
Nuclear Power ◽  
Radiation Safety ◽  
Three Dimensional ◽  
Radiation Shielding ◽  
Storage Facility ◽  
Spent Fuel ◽  
Dry Storage ◽  
Spent Fuel Storage ◽  
Fuel Storage

Radiation safety is an important part of safety assessment of spent fuel dry storage technology. This paper describes the radiation protection design of PWR spent fuel dry storage facility for radiation safety completed by China General Nuclear Power Corporation. Considering the special site conditions, Monte Carlo method is used to complete the precise calculation of the three-dimensional radiation dose field in the spent fuel storage building. Through the spent fuel storage module and the storage building with shielding function, radiation shielding design is completed to meet China’s regulatory requirements, which ensures radiation safety for workers and the public during the transport and storage of spent fuel. It will provide a reference for construction of spent fuel dry storage facility of CPR1000 and HPR1000.

The interim fuel storage facility of the PBMR

2005 ◽  
Vol 32 (17) ◽  
pp. 1854-1866 ◽  
Author(s):  
W.F. Fuls ◽  
C. Viljoen ◽  
C. Stoker ◽  
C. Koch ◽  
M. Kleingeld
Keyword(s):  
Storage Facility ◽  
Fuel Storage

Design of the Spent Fuel Storage Well of HTR-PM

2016 ◽  
Author(s):  
Jinhua Wang ◽  
Bing Wang ◽  
Bin Wu ◽  
Yue Li
Keyword(s):  
High Temperature ◽  
Storage System ◽  
Inherent Safety ◽  
Storage Facility ◽  
Spent Fuel ◽  
Hot Air ◽  
Spent Fuel Storage ◽  
Fuel Storage ◽  
Water Reactors ◽  
Residual Heat

There are more than 400 reactors in operation to generate electricity in the world, most of them are pressurized water reactors and boiling water reactors, which generate great amount of spent fuel every year. The residual heat power of the spent fuel just discharged from the reactor core is high, it is required to store the spent fuel in the spent fuel storage pool at the first 5 years after discharged from the reactor, and then the spent fuel could be moved to the interim storage facility for long term storage, or be moved to the factory for final treatment. In the accident of the Fukushima in 2011, the spent fuel pool ruptured, which led to the loss of coolant accident, it was very danger to the spent fuel assemblies stored in the pool. On the other hand, the spent fuel stored in the dry storage facility was safe in the whole process of earthquake and tsunami, which proved inherent safety of the spent fuel dry storage facility. In china, the High Temperature gas cooled Reactor (HTR) is developing for a long time in support of the government. At the first stage, HTR-10 with 10MW thermal power was designed and constructed in the Institute of Nuclear Energy Technology (INET) of Tsinghua University, and then the High Temperature Reactor-Pebble bed Modules (HTR-PM) is designed to meet the commercial application, which is in constructing process in Shandong Province. HTR has some features of the generation four nuclear power plant, including inherent safety, avoiding nuclear proliferation, could generate high temperature industrial heat, and so on. Spherical fuel elements would be used as fuel in HTR-PM, there are many coating fuel particles separated in the fuel element. As the fuel is different for the HTR and the PWR, the fuel element would be discharged into the appropriate spent fuel canister, and the canister would be stored in the appropriate interim storage facility. As the residual power density is very low for the spent fuel of HTR, the spent fuel canister could be cooled with air ventilation without water cooling process. The advantage of air cooling mode is that it is no need to consider the residual heat removal depravation due to loss of coolant accident, so as to increase the inherent safety of the spent fuel storage system. This paper introduced the design, arrangement and safety characteristics of the spent fuel storage well of HTR-PM. The spent fuel storage wells have enough capacity to hold the total spent fuel canisters for the HTR-PM. The spent fuel storage facility includes several storage wells, cold intake cabin, hot air discharge cabin, heat shield cylinders, well lids and so on. The cold intake cabin links the inlets of all the wells, which would be used to import cold air to every well. The hot air discharge cabin links the outlets of all the wells, which would be used to gather heated air discharged from every well, the heated air would be discharged to the atmosphere through the ventilating pipe at the top of the hot air cabin. The design of the spent fuel storage well and the ventilating pipe could discharge the residual heat of the spent fuel canisters in the storage wells, which could ensure the operating safety of the spent fuel storage system.

Sign in / Sign up

Export Citation Format

Share Document