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Extra resources for Terms for Describing New, Advanced Nuclear Powerplants (IAEA TECDOC-936)

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3] 35 For three-dimensional parallelepiped stacking of the containers it is reasonable to assume that the interaction parameter for non-coplanar containers is equal to that for coplanar containers at the same separation. Then proceeding as above it is found that N < 60 for safety, (ii) N o w assume that q oc e~ /d. 2). F o r brevity write fi for the attenuation factor in the wood (function of a). Then on the same assumptions as used above it can be shown that the safety criterion for the infinite three-dimensional lattice is ad F o r the array of fully loaded containers this condition is satisfied if n is less than 0-252.

The sr n sr sb n n 46 CALCULATIONAL METHODS FOR INTERACTING ARRAYS location of the source and the angular distribution and energy spectrum of the emitted neutrons may be varied at will, and a complete range of multiplications, albedos and transmissions can, therefore, be covered. An advantage of the M o n t e Carlo method is that there is n o longer the restriction to spherical symmetry. In addition to allowing the treatment of non-spherical bodies this also means that a single point source may be simulated, enabling information to be gained not only about the surface multiplication of the body but also about the spatial distribution of the emitted neutrons.

2 The experimental method The principle of the method of measurement is as follows. To measure the output induced in a fissile target at A (see Fig. 5) due to a source at B the following count rates are measured. f Usually small mock fission sources, Po-B, F, Be, Na (a, ri), with outputs of about 10 neutrons/sec are used. 6 30 CALCULATIONAL METHODS FOR INTERACTING ARRAYS (i) (ii) (iii) (iv) Source at A Fissile body Source at B Fissile body alone ( C J . at A alone ( C ) . alone ( C ) . at A, source at B ( C ) .

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