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Elevated temperature microcantilever testing of fresh U-10Mo fuel

Journal Article · · Journal of Nuclear Materials
 [1];  [2];  [3];  [3];  [3];  [4]
  1. Univ. of California, Berkeley, CA (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States); Studsvik Nuclear AB, Nyköping (Sweden)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  4. Univ. of California, Berkeley, CA (United States); Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)
+ Show Author Affiliations
Proliferation concerns are the driving force to reduce the enrichment of research reactor fuel from highly enriched fuel to lower levels of enriched fuel. One promising fuel alloy that would enable a reduction in enrichment without greatly diminishing fuel performance is Uranium with 10 wt. % Molybdenum (U-10 wt-% Mo). While there is a large amount of data available on the microstructure and thermal properties of this new fuel type currently there is insufficient data available on the mechanical properties. Small scale mechanical testing techniques can be used to evaluate the mechanical properties of the as-fabricated U-10 wt% Mo components at their intended operating temperature which should improve the accuracy of the input parameters employed by modelers. In this study the mechanical properties of a U-10 wt% Mo fuel meat sample taken from an as-fabricated fuel plate for a new fuel design were evaluated using in-situ scanning electron microscopy microcantilever testing under varying temperatures between room temperature and 200 °C.
Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
89233218CNA000001
OSTI ID:
1558066
Alternate ID(s):
OSTI ID: 1691931
OSTI ID: 22882251
Report Number(s):
LA-UR--19-22332
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 526; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

Figures / Tables (7)

Figure 1(p. 12)figure Figure 1
Figure 2(p. 13)figure Figure 2
Figure 3(p. 14)figure Figure 3
Figure 4(p. 14)figure Figure 4
Figure 5(p. 15)figure Figure 5
Figure 6(p. 15)figure Figure 6
Table 1(p. 16)table Table 1

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS