Material densities Clause Samples

Material densities. ‌ The design fuel material data are summarized in Table 3. Based on this the total amount and the number density of the individual heavy metal isotopes are given as follows. For the number density of Pu isotopes (and Am-241) in a core having ∆R percent of radial and ∆H percent of axial expansion the following stands: ρPuC Pufr,i N ∆R,∆H = Vfuel,IC · MPuC · 100 ; ∆R 2 100 1 + ∆H 100 ρPuC Pufr,i N ∆R,∆H = Vfuel,OC · MPuC · 100 ∆R 2 100 1 + ∆H 100 Note that cIC = P uC and cOC = P uC are simply the volume fraction of PuC in the inner and Pu Vfuel,IC Pu Vfuel,OC the outer core respectively (given in Table 3). For the U isotopes we have: 1 − PuC ρUC Ufr,i N ∆R,∆H = Vfuel,IC MUC 100 · N ; ∆R 2 100 1 + ∆H 100 1 − PuC ρUC Ufr,i N ∆R,∆H = Vfuel,OC MUC 100 · N . ∆R 2 100 1 + ∆H 1 + ∆ H