Neutron irradiated sulfur was sublimed in a N₂ gas stream leaving ³²P produced by the ³²S (n, p)³²P reaction in the quartz bottle. This ³²P was extracted and converted into orthophosphoric acid by boiling for 3-4hr with 0.1N hydrochloric acid. The solution was purified by passage through a cation-exchange resin column. Before irradiation, the sulfur target was purified four times by sublimation.
The resulting ³²P product did not contain any radiochemical impurity except ³³P from side reaction. The chemical form was orthophosphoric acid, its recovery rate being 98%.
The ³²P prepared by this method was measured for specific activity, total solid, acidity, heavy metal content, etc. This method is suitable for routine production of ³²P.

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An experimental study of the void coefficient of reactivity in HTR was carried out. The experiment consisted of an out-of-pile experiment on void ratio calibration and an in-pile experiment on reactivity measurement.
A stream of nitrogen gas was introduced through a pipe to the bottom of a fuel channel to produce a rising column of void bubbles. The reactivity was derived from either rod position or positive period.
The local void coefficients measured were:
(a) Single channel void coefficient
(b) Two channel void coefficient
(c) Three channel void coefficient
From (a), (b), (c) the average void coefficient of HTR was determined to be Δk/k=-1.4×1.07×10^-3/%void.

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U.S. AEC has recently revised its standard table of enriching services. The new schedule of base charges for enriched and depleted uranium in the form of UF₆ can be computed according to formulas in the theory of ideal cascade on the basis of taking natural uranium having on assay of 0.711w/0 ²³⁵U as having a zero separative work component and on the basis of a tails assay of 0.20w/0 ²³⁵U. No optimization of the size of stripping section is made in the schedule.
An estimate of separative work costs and capacities of enriching facilities in UK, France and Red China is formed.

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