Properties of a Fissium-Type Alloy

Saller, H.A.; Dickerson, R.F.; Bauer, A.A.; Daniel, Norman E.

doi:10.2172/4347233

Cited by 6 publications

(6 citation statements)

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“…9 gives an overview of the known thermal conductivity values for UMo alloys with a molybdenum content close to 8 wt.%. While the thermal conductivity for UMo alloys with 5 wt.% Mo [17,18] is higher than for U8Mo between 50°C and 230°C, the alloys with 10 or more wt.% Mo [18][19][20][21] have a lower thermal conductivity. The literature values for 9 wt.% [22] and 9.2 wt.% [23] show good agreement with the measured U8Mo data.…”

Section: Thermal Conductivitymentioning

confidence: 99%

Physical properties of monolithic U8wt.%–Mo

Hengstler¹,

Beck

Breitkreutz

et al. 2010

Journal of Nuclear Materials

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Section: Thermal Conductivitymentioning

confidence: 99%

Physical properties of monolithic U8wt.%–Mo

Hengstler¹,

Beck

Breitkreutz

et al. 2010

Journal of Nuclear Materials

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“…The evolution of the peak temperature at the fuel centreline, at the fuel surface and in the coolant is shown in Figure . As foreseen in the experiment analysis, the temperatures rise but remain within an acceptable margin of safety limits (sodium vaporisation in atmospheric conditions occurs at 1154.7 K ± 1.3 K , while the melting temperature of the fissium fuel onset begins at approximately 1283 K and concludes at approximately 1373 K ). As anticipated from the physics aspects which are modelled, peak temperatures occur in correspondence to the maximum feedback reactivity.…”

Section: Transient Resultsmentioning

confidence: 85%

Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient

et al. 2016

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SUMMARYDuring the last decade the European activities in the field of nuclear fission research include the design of fast reactors cooled by liquid metals. Within this framework, the Fast REactor NEutronics/Thermal-hydraulICs (FRENETIC) code is being developed at Politecnico di Torino over the last few years. It implements a full-core coupled neutronic/thermalhydraulic model of a liquid-metal-cooled fast reactor as relevant for two of the six options currently under study within the framework of the Generation-IV International Forum, namely the lead-cooled fast reactors and the sodium-cooled fast reactors. The code validation process involves the participation in a coordinated research project of the International Atomic Energy Agency, aiming at testing different computational tools against the shutdown heat removal tests performed many years ago in the sodium-cooled Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory, USA. In this paper, results of the FRENETIC analysis of one of the transients considered in the project, the unprotected EBR-II shutdown heat removal test SHRT-45R, are presented and compared to the measurements, providing the first validation of the coupled neutronic/thermal-hydraulic features of the FRENETIC code.

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“…Data for unirradiated U-Mo alloys are available for U-5Mo [36], U-8Mo [37,38], U-9Mo [39,40], U-10Mo [12,14,23,41,42], and U-12Mo [37], all of which are shown in Figure 2.11below. The tabulated data values can be found in Appendix B: The UMo handbook [43] had done an analysis and fit of this data, but errors were found in the data set used to develop the fit, so re-analysis was needed.…”

Section: Unirradiated Thermal Conductivity Of U-mo Alloysmentioning

confidence: 99%

“…11. Thermal conductivity dependence on temperature for selected data sets [12,14,23,29,36,37,38,39,40,41,42,43] .19. Comparison of the Preliminary UMo Report [1], fit of current best data (equation 2.35), the current best data set [58], and the value utilized for HFIR analyses [3] Comparison of the CTE assumed by analyses for HFIR [3], the Preliminary UMo Report [1], and the fit of current best data (equation 3 [98,99].…”

mentioning

confidence: 99%