Concepedia

Study on the mechanical properties and thermal conductivity of silicon carbide-, zirconia- and magnesia aluminate-based simulated inert matrix nuclear fuel materials after cyclic thermal shock

Y.W. Lee, S.C. Lee, H.S. Kim, C.Y. Joung, C. Degueldre

Journal of Nuclear Materials · 2003 · 20 citations · 7 references

DOI

Concepts

References

7

Equilibrium penny-like cracks in indentation fracture

Brian R. Lawn, Edwin R. Fuller · Journal of Materials Science · 1975 · 742 citations

, , +12

Silicon carbide as an inert-matrix for a thermal reactor fuel

R.A. Verrall, M. D. Vlajic, V. D. Krstic · Journal of Nuclear Materials · 1999 · 102 citations

, , +14

Melting point of MgO

C. Ronchi, M. Sheindlin · Journal of Applied Physics · 2001 · 81 citations

, , +14

Inert matrix fuel for the utilisation of plutonium

G. Ledergerber, C. Degueldre, P. Heimgartner et al. · Progress in Nuclear Energy · 2001 · 73 citations

, , +12

Preparation of simulated inert matrix fuel with different powders by dry milling method

Y.-W Lee, H.S Kim, S.H Kim et al. · Journal of Nuclear Materials · 1999 · 73 citations

, , +15