scholarly journals Status of the irradiation test vehicle for testing fusion materials in the Advanced Test Reactor

1998 ◽  
Author(s):  
H Tsai ◽  
I C Gomes ◽  
D L Smith ◽  
A J Palmer ◽  
F W Ingram ◽  
...  
Keyword(s):  
Test Vehicle ◽  
Fusion Materials ◽  
Irradiation Test ◽  
Test Reactor

Comparison of Predictive and Experimental Data From Graphite Irradiations in the Advanced Test Reactor Irradiation Test Vehicle

2003 ◽  
Author(s):  
Richard G. Ambrosek ◽  
Debbie J. Utterbeck
Keyword(s):  
Physical Property ◽  
The United States ◽  
Physical Structure ◽  
Experimental Results ◽  
United States Department ◽  
Test Vehicle ◽  
Irradiation Test ◽  
Environmental Laboratory ◽  
Test Reactor ◽  
The Individual

In 2000, British Nuclear Fuels Limited (BNFL) commissioned an irradiation program at the United States Department of Energy’s Idaho National Engineering and Environmental Laboratory (INEEL) to assess the effects of extended operating scenarios upon the integrity of Magnox reactor cores. In this program, predictions of thermal and physical effects on these graphite cores were developed using analytical computer models. To benchmark results, experimental graphite assemblies representative of the Magnox graphite were irradiated in the Advanced Test Reactor (ATR). This paper analyzes and contrasts the thermal predictions with those experimental results. These investigations were conducted to extend existing graphite physical property databases for higher radiolytic weight loss (35–50% density reduction) than occur during the economic planning life of these reactors. These data then can be used to make extended life projections regarding the suitable function of the graphite in its various roles of providing the physical structure for the fuel, neutron moderator, medium for instrumentation, and coolant channels. Extended irradiation effects will be obtained with samples of archived, pre-characterized graphite used in the Magnox type reactors. The new Irradiation Test Vehicle (ITV) facility in the ATR contained the experiments and provided the desired irradiation conditions as well as on-line temperature control. The capability to provide both oxidizing and inert gas atmospheres for the graphite specimens was added to the ITV to enable assessment of the individual and combined effects of oxidation and neutron damage to the specimens. In this paper the thermal evaluations (performed to size the control gaps to obtain the desired thermal performance) are contrasted to actual experimental results.

FFTF as an irradiation test bed for fusion materials and components

1986 ◽  
Vol 141-143 ◽  
pp. 1032-1038 ◽  
Author(s):  
D.L. Greenslade ◽  
R.J. Puigh ◽  
G.W. Hollenberg ◽  
J.M. Grover
Keyword(s):  
Test Bed ◽  
Fusion Materials ◽  
Irradiation Test

scholarly journals Fmit-The Fusion Materials Irradiation Test Facility

1981 ◽  
Vol 28 (2) ◽  
pp. 1304-1307 ◽  
Author(s):  
Don Liska ◽  
Milton D. Machalek
Keyword(s):  
Test Facility ◽  
Fusion Materials ◽  
Irradiation Test

Fusion Materials Irradiation Test Facility a Facility for Fusion Materials Qualification

1983 ◽  
Vol 4 (2P2) ◽  
pp. 695-700 ◽  
Author(s):  
A. L. Trego ◽  
J. W. Hagan ◽  
E. K. Opperman ◽  
R. J. Burke
Keyword(s):  
Test Facility ◽  
Fusion Materials ◽  
Irradiation Test

scholarly journals Damage parameters for candidate fusion materials irradiation test facilities

1990 ◽  
Vol 174 (2-3) ◽  
pp. 125-134 ◽  
Author(s):  
D.G. Doran ◽  
F.M. Mann ◽  
L.R. Greenwood
Keyword(s):  
Fusion Materials ◽  
Irradiation Test
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