scholarly journals Stability of γ-UMo Nuclear Fuel Alloys by Thermal Analysis

10.5772/53340 ◽  
2013 ◽  
Author(s):  
Fabio Branco Vaz de Oliveira ◽  
Delvonei Alves de Andrade
Keyword(s):  
Thermal Analysis ◽  
Nuclear Fuel

Thermal Analysis for Geologic Codisposal of SNF Packages

2002 ◽  
Author(s):  
Si Y. Lee
Keyword(s):  
Thermal Analysis ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Peripheral Region ◽  
Waste Form ◽  
Temperature History ◽  
High Level Waste ◽  
Geologic Repository ◽  
Geologic Disposal ◽  
High Level

The engineering viability of disposal of aluminum-clad, aluminum-based spent nuclear fuel (Al-SNF) in a geologic repository requires a thermal analysis to provide the temperature history of the waste form. Calculated temperatures are used to demonstrate compliance with criteria for waste acceptance into the geologic disposal system and as input to assess the chemical and physical behavior of the waste form within the Waste Package (WP). The leading codisposal WP design proposes that a central DOE Al-SNF canister be surrounded by five Defense Waste Process Facility (DWPF) glass log canisters, that is, High-level Waste Glass Logs (HWGL’s), and placed into a WP in a geologic disposal system. A DOE SNF canister having about 0.4318m diameter is placed along the central horizontal axis of the WP. The five HWGL’s will be located around the peripheral region of the DOE SNF canister within the cylindrical WP container. The codisposal WP will be laid down horizontally in a drift repository. In this situation, two waste form options for Al-SNF disposition are considered using the codisposal WP design configurations. They are the direct Al-SNF form and the melt-dilute ingot. In the present work, the reference geologic and design conditions are assumed for the analysis even though the detailed package design is continuously evolved. This paper primarily dealt with the thermal performance internal to the codisposal WP for the qualification study of the WP containing Al-SNF. Thermal analysis methodology and decay heat source terms have been developed to calculate peak temperatures and temperature profiles of Al-SNF package in the DOE spent nuclear fuel canister within the geologic codisposal WP.

Methodology for thermal analysis of spent nuclear fuel dry cask using CFD codes

2019 ◽  
Vol 133 ◽  
pp. 257-274 ◽  
Author(s):  
Julio Benavides ◽  
Gonzalo Jimenez ◽  
Marta Galbán ◽  
Miriam Lloret
Keyword(s):  
Thermal Analysis ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel

The Thermal Expansion Coefficient of Dispersion Nuclear Fuel Elements

2014 ◽  
Vol 1039 ◽  
pp. 85-90
Author(s):  
Li Nie ◽  
Xiao Gang Wang ◽  
Xin Jiang ◽  
Chang Tao Pang
Keyword(s):  
Thermal Analysis ◽  
Thermal Expansion ◽  
Thermal Expansion Coefficient ◽  
Nuclear Fuel ◽  
Expansion Coefficient ◽  
Representative Volume Element ◽  
Theoretical Models ◽  
Volume Element ◽  
Dispersion Fuel ◽  
Fuel Elements

A representative volume element is chosen to act as the research object to analyze the thermal expansion coefficient of the dispersion fuel elements. The thermal analysis is carried out for the thermal behaviors using FEM. The results are compared with several theoretical models.

Thermal analysis of CASTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

2017 ◽  
Vol 99 ◽  
pp. 40-46 ◽  
Author(s):  
R. Poškas ◽  
V. Šimonis ◽  
P. Poškas ◽  
A. Sirvydas
Keyword(s):  
Thermal Analysis ◽  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Long Term Storage ◽  
Term Storage
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