The spectra were calculated by the MCNP 4A code, using as input the leakage spectrum from the core calculated earlier. The spectra were normalized to 1 neutron.cm^-2.s^-1 and presented as flux per unit lethargy (logarithmical energy).

Thermal neutrons were not calculated but measured to spare run time and have statistics good enough. It is observable that the intermediate (1/E) part extends up to ∼10 keV, the fast section has a peak at about 1 MeV for both spectra. These spectra can be considered as quite hard ones with low dose and flux as shown in Table 2.

Table 2. Flux and dose values calculated and measured (see Fig. 8.)

	Lead filter		Bismuth filter
Intermed. flux ratio, %	40.8		39.5
Fast flux ratio, %	59.2		60.5
Measured thermal flux	520*	1180	1050
Measured intermed. flux	5700		14000
Fitted fast flux	8200		21000
Total flax	14420*	15080	36050
H* conversion factor**		167	171
Hp conversion factor**		175	179

Fluxes are given in neutron.cm^-2.s^-1
*additional 8 mm Al and 10 mm B₄C filter combination
^**in pSv.cm²