A New Criterion for the Degradation of a Defective Spent Fuel Rod under Dry Storage Conditions Based on Nuclear Ceramic Cracking

2008 ◽  
Vol 1124 ◽  
Author(s):  
Lionel Desgranges ◽  
François Charollais ◽  
Isabelle Felines ◽  
Cécile Ferry ◽  
Jean Radwan
Keyword(s):  
Storage Condition ◽  
Storage Conditions ◽  
Nuclear Fuels ◽  
Spent Fuel ◽  
Coated Particles ◽  
Fuel Rod ◽  
Dry Storage ◽  
Fuel Particles ◽  
New Criterion ◽  
Environmental Sem

AbstractExperimental results using environmental SEM on intentionally defected fuel particles showed that oxidation induced cracking could lead to the degradation of HTR coated particles. The interpretation proposed for the swelling resulting from cracking can be extended to irradiated nuclear fuels. That is why a new criterion was proposed to defined safe handling of defective fuel in dry storage condition. This criterion defines the time needed to create an oxidized layer thickness leading to significant cracking.

Using CFD Couple with Visual Basic to Investigate the Thermal Behavior for Fuel Rod Bowing Problem

2013 ◽  
Vol 651 ◽  
pp. 688-693
Author(s):  
Wei Keng Lin ◽  
Jong Rong Wang ◽  
Yung Shin Tseng ◽  
Jui En Chang
Keyword(s):  
Cfd Simulation ◽  
Storage System ◽  
Visual Basic ◽  
Spent Fuel ◽  
Rod Bundles ◽  
Concentric Cylinder ◽  
Structure Deformation ◽  
Fuel Rod ◽  
Dry Storage ◽  
Fuel Elements

Nuclear fuel elements assemblies are generally consists of fuel rod bundles; each bundle is a concentric cylinder with three layers. Taking GE-8X8 for example, there is pellet, gap, and cladding from inside to outside. The diameter for each concentric cylinder is 9.26cm, 9.47cm, and 10.71cm respectively. In reality, a structure deformation may happen to those components due to the reason of radiation result in the high temperature of the bundles system. For the space of gap decreases by the expansion of pellet, the thermal conductivity might be under predicted and there is not enough study about this topic yet. To improve the accuracy of PRAs, more studies of the shrink phenomena on the gap between pellet and cladding are necessary. In this study, we had developed a program on the purpose of processes improvement for CFD simulation about spent fuel dry storage system. The program can adjust the dimension for each part of formation very friendly. We think it can also do some help on the needs if we want to compare the performance on heat transfer for different fraction on each part of bundle. In addition, the axial power distributions of the rod were also defined file by the user very easy, the results shown no obviously temperature difference between the full gap and 90% reduction of the gap.

scholarly journals Oxidation of Fuel Rod under Dry Storage Condition

1995 ◽  
Vol 32 (4) ◽  
pp. 321-332 ◽  
Author(s):  
Jinichi NAKAMURA ◽  
Takashi OTOMO ◽  
Teruo KIKUCHI ◽  
Satoru KAWASAKI
Keyword(s):  
Storage Condition ◽  
Fuel Rod ◽  
Dry Storage

scholarly journals Benchmark Experiments for Steady-State Natural Convection in Fuel Rod Bundles

2017 ◽  
Vol 2 (2) ◽  
Author(s):  
Kyle L. Jones ◽  
Barton L. Smith
Keyword(s):  
Natural Convection ◽  
The Body ◽  
Stereoscopic Particle Image Velocimetry ◽  
System Response ◽  
Spent Fuel ◽  
Rod Bundles ◽  
Validation Data ◽  
Pressurized Water ◽  
Fuel Rod ◽  
Dry Storage

Natural convection is a phenomenon in which fluid flow surrounding a body is induced by a change in density due to the temperature difference between the body and fluid. After removal from the pressurized water reactor (PWR), decay heat is removed from nuclear fuel bundles by natural convection in spent fuel pools for up to several years. Once the fuel bundles have cooled sufficiently, they are removed from fuel pools and placed in dry storage casks for long-term disposal. Little is known about the convective effects that occur inside the rod bundles under dry-storage conditions. Simulations may provide further insight into spent-fuel dry storage, but the models used must be evaluated to determine their accuracy using validation methods. The present study investigates natural convection in a 2 × 2 fuel rod model in order to provide validation data. The four heated aluminum rods are suspended in an open-circuit wind tunnel. Boundary conditions (BCs) have been measured and uncertainties calculated to provide necessary quantities to successfully conduct a validation exercise. System response quantities (SRQs) have been measured for comparing the simulation output to the experiment. Stereoscopic particle image velocimetry (SPIV) was used to nonintrusively measure three-component velocity fields. Two constant-heat-flux rod surface conditions are presented, 400 W/m2 and 700 W/m2, resulting in Rayleigh numbers of 4.5 × 109 and 5.5 × 109 and Reynolds numbers of 3450 and 4600, respectively. Uncertainty for all the measured variables is reported.

Behavior of a Defective Nuclear Fuel Rod in Dry Storage Conditions Studied with a New Experimental Setup

2008 ◽  
Vol 163 (2) ◽  
pp. 252-260 ◽  
Author(s):  
L. Desgranges ◽  
M. P. Ferroud-Plattet ◽  
R. Alloncle ◽  
I. Aubrun ◽  
J. M. Untrau ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Storage Conditions ◽  
Experimental Setup ◽  
Fuel Rod ◽  
Dry Storage

Drying of Spent Nuclear Fuels and Fuel Debris Dried in a Vacuum Furnace

2001 ◽  
Author(s):  
Allan B. Christensen ◽  
Kraig M. Wendt
Keyword(s):  
Vacuum Drying ◽  
Vacuum Furnace ◽  
Nuclear Fuels ◽  
Spent Fuel ◽  
Drying Method ◽  
Drying Process ◽  
Dry Storage ◽  
Environmental Laboratory ◽  
Alloy Carbide ◽  
Fuel Material

Abstract Spent nuclear fuels and fuel debris stored underwater must eventually be prepared for dry storage (e.g., repository disposition). This preparation involves some degree of fuel drying. Primary considerations for a fuel drying process are the containment configuration of the spent fuel material and the type of fuel material (e.g., oxide, metal, hydride, alloy, carbide, epoxied, debris). The Idaho National Engineering and Environmental Laboratory has built and operated three heated vacuum drying systems and placed into interim dry storage all of these fuel types. The drying systems and process have been tested and modeled so that the extent of dryness can be predicted and used to plan and perform drying operations. This paper presents this drying method.

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