1971
DOI: 10.1016/0029-5493(70)90159-7
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Hydrides as neutron moderator and reflector materials

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Cited by 62 publications
(38 citation statements)
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“…The bulk density of YH 2 is smaller than that of ZrH 2 and the dissociation temperature of YH 2 is 1200 °C, which is 300 °C higher than that of ZrH 2 . These physical and chemical properties may help to avoid thermal spikes 42 , 43 . Furthermore, we have revealed that the thermal spike observed for ZrH 2 can be suppressed by using the deuteride (ZrD 2 ) instead of the hydride 44 .…”
Section: Introductionmentioning
confidence: 99%
“…The bulk density of YH 2 is smaller than that of ZrH 2 and the dissociation temperature of YH 2 is 1200 °C, which is 300 °C higher than that of ZrH 2 . These physical and chemical properties may help to avoid thermal spikes 42 , 43 . Furthermore, we have revealed that the thermal spike observed for ZrH 2 can be suppressed by using the deuteride (ZrD 2 ) instead of the hydride 44 .…”
Section: Introductionmentioning
confidence: 99%
“…If a reasonably low partial pressure (~1 atm) is needed, either calcium hydride (liquid phase or liquid-solid mixture) [17], yttrium hydride (solid phase) [18], or some lanthanide hydrides can be adopted (see Figure 1 , which summarizes data in Ref. [1]). If higher hydrogen partial pressure in the moderator enclosure is acceptable, zirconium and titanium hydrides may also be used.…”
Section: Literature Review On Advanced Moderator Materialsmentioning
confidence: 99%
“…High-temperature core concepts traditionally rely on graphite to moderate neutrons since it can sustain high temperatures and displays very low absorption cross-sections. However, it is much less efficient at slowing-down neutrons when compared with a hydrogen-based material [1]. The direct consequence will be to require a high carbon to U-235 ratio in the core.…”
Section: Introductionmentioning
confidence: 99%
“…Other references indicate problems with the hydrogen embrittlement of yttrium. This effect appears already for low hydrogen content around and below room temperature [29], and a lack of ductility is described for YH 1.7 at temperatures even above the foreseen operation temperature [30]. Another publication gives view on the possibility of cladding the YH with a protective layer.…”
Section: Remarks On Technological Issues and Reactor Experiencementioning
confidence: 99%