scholarly journals Drop Analysis of the Advanced Test Reactor Fresh Fuel Shipping Container with Heavier Low-Enriched Uranium Fuel Contents

2020 ◽  
Author(s):  
Robert Spears
Keyword(s):  
Shipping Container ◽  
Uranium Fuel ◽  
Enriched Uranium ◽  
Test Reactor

Effects of Thickness of Zirconium Liner on Stress-Strain Characteristics of U10Mo Monolithic Plates

2013 ◽  
Author(s):  
Hakan Ozaltun ◽  
Robert M. Allen ◽  
You Sung Han
Keyword(s):  
Diffusion Barrier ◽  
Reactor Core ◽  
Stress Strain ◽  
Strain Behavior ◽  
Uranium Fuel ◽  
Plate Design ◽  
Enriched Uranium ◽  
Test Reactor ◽  
Irradiation Performance ◽  
Fuel Elements

The effects of the thickness of Zirconium liner on stress-strain behavior of monolithic fuel mini-plates during fabrication and irradiation processes were studied. Monolithic plate-type fuel elements is a new fuel form being developed for research and test reactors to achieve higher uranium densities which allows the use of low-enriched uranium fuel in reactor core. These fuel elements are comprised of a high density, low enrichment, U–Mo alloy based fuel foil encapsulated in a cladding material made of Aluminum. Early RERTR experiments indicated that the presence of an interaction layer between the fuel and cladding materials causes mechanical problems. To minimize the fuel/cladding interaction, employing a diffusion barrier between the cladding and the fuel materials was proposed. Current monolithic plate design employs a 0.025 mm thick, 99.8% pure annealed Zirconium diffusion barrier between the fuel foil (U10Mo) and the cladding materials (AL6061-O). To benchmark the irradiation performance, a number of plates were irradiated in the Advanced Test Reactor (ATR) with promising irradiation performance. To understand the effects of the thickness of the Zirconium diffusion barrier on the stress-strain behavior of the plates during fabrication, irradiation and shutdown stages, a representative plate from RERTR-12 experiments (Plate L1P7A0) was selected and simulated. Both fabrication and irradiation stages were considered. Simulations were repeated for various Zirconium thicknesses to understand the effects of the thickness of the diffusion barrier. Results of fabrication simulations indicated that Zirconium thickness has noticeable effects on foil’s stresses. Irradiation simulations revealed that the fabrication stresses of the foil would be relieved rapidly in the reactor. Results also showed that Zirconium thickness has little or no effects on irradiation and shutdown stresses.

The Current Status of Converting the University of Missouri Research Reactor from Highly Enriched Uranium to Low-Enriched Uranium Fuel

2020 ◽  
Author(s):  
A. Moisseytsev ◽  
D. Yoon ◽  
E. Feldman ◽  
J. Stillman ◽  
K. Kutikkad ◽  
...  
Keyword(s):  
Research Reactor ◽  
Current Status ◽  
University Of Missouri ◽  
Uranium Fuel ◽  
Enriched Uranium ◽  
The University

Preliminary Core Design and Optimization Analysis of Travelling Wave Reactor

2014 ◽  
Vol 1070-1072 ◽  
pp. 357-360
Author(s):  
Dao Xiang Shen ◽  
Yao Li Zhang ◽  
Qi Xun Guo
Keyword(s):  
Monte Carlo ◽  
Rational Design ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Travelling Wave ◽  
Optimization Analysis ◽  
Design And Optimization ◽  
Uranium Fuel ◽  
Enriched Uranium ◽  
Ignition Zone

A travelling wave reactor (TWR) is an advanced nuclear reactor which is capable of running for decades given only depleted uranium fuel, it is considered one of the most promising solutions for nonproliferation. A preliminary core design was proposed in this paper. The calculation was performed by Monte Carlo method. The burning mechanism of the reactor core design was studied. Optimization on the ignition zone was performed to reduce the amount of enriched uranium initially deployed. The results showed that the preliminary core design was feasible. The optimization analysis showed that the amount of enriched uranium could be reduced under rational design.

scholarly journals Fuel – clad chemical interaction evaluation of the TREAT reactor conceptual low-enriched-uranium fuel element

2018 ◽  
Vol 512 ◽  
pp. 252-267 ◽  
Author(s):  
C.J. Parga ◽  
I.J. van Rooyen ◽  
E.P. Luther
Keyword(s):  
Fuel Element ◽  
Chemical Interaction ◽  
Uranium Fuel ◽  
Enriched Uranium

Preliminary Assessment of Structural Behavior of MITR Low-Enriched Uranium Fuel Plates

2020 ◽  
Author(s):  
C. Cetinbas ◽  
E. Wilson ◽  
W. Mohamed ◽  
H. Roh
Keyword(s):  
Structural Behavior ◽  
Preliminary Assessment ◽  
Uranium Fuel ◽  
Enriched Uranium

Licensing of the ES-3100 Type B Shipping Container: Replacement of the DOT 6M Container

2005 ◽  
Author(s):  
Jeffrey G. Arbital ◽  
Dean R. Tousley ◽  
James C. Anderson
Keyword(s):  
State Of The Art ◽  
Nuclear Regulatory Commission ◽  
Department Of Energy ◽  
Radioactive Material ◽  
Shipping Container ◽  
Nuclear Security ◽  
Material Transportation ◽  
Enriched Uranium ◽  
Regulatory Commission ◽  
The U.S

The National Nuclear Security Administration (NNSA) is shipping bulk quantities of fissile materials for disposition purposes, primarily highly enriched uranium (HEU), over the next 15 to 20 years. The U.S. Department of Transportation (DOT) specification 6M container has been the workhorse for NNSA and many other shippers of radioactive material. However, the 6M does not conform to the safety requirements in the Code of Federal Regulations (10 CFR 71[1]) and, for that reason, is being phased out for use in the secure transportation system of the U.S. Department of Energy (DOE) in early 2006. BWXT Y-12 is currently developing the replacement for the DOT 6M container for NNSA and other users. The new package is based on state-of-the-art, proven, and patented technologies that have been successfully applied in the design of other packages. The new package will have a 50% greater capacity for HEU than the 6M, and it will be easier to use with a state-of-the-art closure system on the containment vessel. This new package is extremely important to the future of fissile, radioactive material transportation. An application for license was submitted to the U.S. Nuclear Regulatory Commission (NRC) in February 2005. This paper reviews the license submittal, the licensing process, and the proposed contents of this new state-of-the-art shipping container.

Lattice optimization for graphite moderated molten salt reactors using low-enriched uranium fuel

2017 ◽  
Vol 110 ◽  
pp. 1-10 ◽  
Author(s):  
Dallas Moser ◽  
Alexander Wheeler ◽  
Ondřej Chvála
Keyword(s):  
Molten Salt ◽  
Uranium Fuel ◽  
Enriched Uranium
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