Fueling Machine Model for Simulation of Spent Fuel Behavior in Postulated Fuel Handling Accidents

2019 ◽  
Vol 6 (1) ◽  
Author(s):  
L. Y. Huang ◽  
H. Z. Fan ◽  
M. Maltchevski ◽  
A. Ranger
Keyword(s):  
Fission Product ◽  
Heat Removal ◽  
Safety Analysis ◽  
Complex Configuration ◽  
Integral Approach ◽  
Spent Fuel ◽  
Machine Model ◽  
Product Release ◽  
Fuel Behavior ◽  
In Transit

Abstract On-power fueling is an important feature of the CANDU® reactor. Fueling is a routine operation with a large number of channel fueling visits made each year with the fueling machines acting as the key system. Hence, safety analysis must consider fueling machine events typically when the fueling machine is in transit toward the spent fuel port. This paper presents a model of fueling machine containing spent fuel with complex configuration and multiprocess mechanisms. Using an integral approach with fuel and fueling machine, this model tends to improve previous modeling method, which only takes account of a slice of fuel or fueling machine. This fueling machine model is developed for simulations of the fueling machine coolant thermal hydraulics behavior, the spent fuel behavior, and potential fission product release during postulated loss of heat removal accidents. An example of its application is also presented in this paper.

scholarly journals Natural Safety Analysis of the Spent Fuel Residual Heat Removal in Loading and Storage Process of HTR-10

2013 ◽  
Vol 39 ◽  
pp. 227-239 ◽  
Author(s):  
Jin-hua Wang ◽  
Yi-fan Huang ◽  
Yong Tang ◽  
Bin Wu
Keyword(s):  
Heat Removal ◽  
Safety Analysis ◽  
Spent Fuel ◽  
Storage Process ◽  
And Storage ◽  
Residual Heat

Behavior of the Spent Fuel Pool and Dose Rate Calculations for the CPR1000 Reactor Under Severe Accident Conditions Using the Integral Code MELCOR

2013 ◽  
Author(s):  
Klaus Mueller ◽  
Moses Yeung ◽  
Justin Byard ◽  
Zhen Xun Peng ◽  
Jun Tao ◽  
...  
Keyword(s):  
Fission Product ◽  
Dose Rate ◽  
Flow Rate ◽  
Hydrogen Combustion ◽  
Severe Accident ◽  
Pure Hydrogen ◽  
Spent Fuel ◽  
Product Release ◽  
Spent Fuel Pool ◽  
Accident Conditions

The behavior of the spent fuel pool and the fission product release and transport for the CPR1000 reactor under severe accident conditions was analyzed using the integral severe accident code MELCOR. In the investigated accident scenario a total failure of the pump of the spent fuel cooling system was assumed. Furthermore, it is assumed that accident management fails to bring water into the spent fuel pool using mobile pumps or due to the non-recovery of the cooling pump. The grace time available for measures in order to avoid significant fission product release to the environment is determined. The calculated hydrogen mass flow rate due to clad oxidation and the steam flow rate from the spent fuel pool to the compartment above the spent fuel pool serve as boundary conditions for the three dimensional fluid dynamics code GASFLOW to assess possible hydrogen combustion or detonation in the compartment. Using this spent fuel pool MELCOR model the dose submerged in air or water can be determined. The calculated gamma dose rate in a specific compartment can be used for equipment qualification and compartment accessibility assessment. It was found that after four days the fuel assemblies are significantly heated-up and ten hours later the fission products are released as well as a significant amount of hydrogen is produced. A preliminary GASFLOW analysis shows by assuming an air atmosphere in the fuel building, that the risk of a hydrogen combustion or detonation is high. In late state of the accident a convection flow of pure hydrogen is established in spent fuel pool region. It was shown, that the flow conditions strongly influence the fission product transport behavior and consequently the dose rates in the compartment above the spent fuel pool.

scholarly journals CRITICALITY SAFETY ANALYSIS OF THE DRY CASK DESIGN WITH AIR GAPS FOR RDNK SPENT PEBBLE FUELS STORAGECriticality Safety Analysis of the Dry Cask Design with Air Gaps for RDNK Spent Pebble Fuels Storage

2021 ◽  
Vol 23 (3) ◽  
pp. 123
Author(s):  
Pungky Ayu Artiani ◽  
Yuli Purwanto ◽  
Aisyah Aisyah ◽  
Ratiko Ratiko ◽  
Jaka Rachmadetin ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Thermal Power ◽  
Heat Removal ◽  
Threshold Value ◽  
Safety Analysis ◽  
Spent Fuel ◽  
Air Gaps ◽  
Fuel Elements ◽  
Submerged Conditions ◽  
Criticality Safety

Reaktor Daya Non-Komersial (RDNK) with a 10 MW thermal power has been proposed as one of the technology options for the first nuclear power plant program in Indonesia. The reactor is a High Temperature Gas-Cooled Reactor-type with spherical fuel elements called pebbles. To support this program, it is necessary to prepare dry cask to safely store the spent pebble fuels that will be generated by the RDNK. The dry cask design has been proposed based on the Castor THTR/AVR but modified with air gaps to facilitate decay heat removal. The objective of this study is to evaluate criticality safety through keff  value of the proposed dry cask design for the RDNK spent fuel. The keff  values were calculated using MCNP5 program for the dry cask with 25, 50, 75, and 100% of canister capacity. The values were calculated for dry casks with and without air gaps in normal, submerged, tumbled, and both tumbled and submerged conditions. The results of calculated keff  values for the dry cask with air gaps at 100% of canister capacity from the former to the latter conditions were 0.127, 0.539, 0.123, and 0.539, respectively. These keff values were smaller than the criticality threshold value of 0.95. Therefore, it can be concluded that the dry cask with air gaps design comply the criticality safety criteria in the aforementioned conditions.

Fission product release in high-burn-up UO2 oxidized to U3O8

2006 ◽  
Vol 348 (3) ◽  
pp. 229-242 ◽  
Author(s):  
J.Y. Colle ◽  
J.-P. Hiernaut ◽  
D. Papaioannou ◽  
C. Ronchi ◽  
A. Sasahara
Keyword(s):  
Fission Product ◽  
Product Release
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