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F i g . 4 ? 1 \ / / 0 / / / 20 40 60 80 100 Radius, R , cm. F i g . 2 7 SPATIAL FAST, INTERMEDIATE, AND THERMAL FLUX DISTRIBUTIONS W I T H 1/4" BORON SRELL AT OUTER ANNULUS SURFACE -57- 120 shown, each of t h e absorbing s h e l l s between t h e f u e l annulus and t h e heavy water i n t h e IIFRR is capable of handling 60 per cent o r more excess r e a c t i v i t y because of t h e l a r g e c o n t r o l surface exposed t o neutrons. versatile. Thus, t h e HFRR c o n t r o l is q u f t e The worth of an experiment can be determined by i n s e r t i n g an experi- ment with t h e s h e l l s f u l l y lowered, followed by slow withdrawal of t h e s h e l l s , Another f a c t o r whfch was considered was t h e s a f e t y of t h e r e a c t o r i n case a n experiment should f a i l , For t h e purposes of i l l u s t r a t i o n , an experiment containing a concentrated aqueous s o l u t i o n of enriched uranyl s u l f a t e was assumed t o be located i n t h e c e n t e r of t h e "RR.

478 MeV gamma r a y . The lithium which i s formed w i l l combine wfth boric acid t o produce lithium borate, Lifhium borate is fnsoluble i n water so t h a t some means, such as a s e t t l f n g tank, w i l l have t o be provided f o r removing the precipitate. 20 grams of boric acid per gram of water which is about t h e maxfmum concentration t h a t can be a t t a i n e d a t room temperature. Later \r calculations indicated t h a t t h i s concentration was higher than t h a t required f o r control of the HFRR.

I 4 Radius, R, cia. 6 0 IFOUTME FRACTION OF D20 I N CENTER REGION Fig. 18 x 1019 ,'7 \ \ I I /", I I \ \ 1 i . 16 Radius, R , cm. 1 20 0 40 R a d i u s , R , cm. Fig. 1 LA:=-- -- 4 20 Fig. 18 Radius, R, cm. CONSTANT POIaIl THEXMAL FLUX DISTRIBUTION FOR D20, Al, AND Be IN CENTER XEGION -45 - - ORNGLR-3wg. 2 0. 19 RATIOS OF MAXIMUM THERMAL FLUX I N CENTER REGION, I N FUEL ANNULUS, AND IN REFLECTOR TO AVERAGE THERMAL FLUX IN FUEL, VS. 5 0 VOLUME FBACTION OF D20 I N CEN"53 REGION Fig. 20 AVERAGE WTEFW3lLATE AND FAST FLUXES I N CENTER REGION TO AirERAGE INTERMEDIATE AND FAST FLUXES I N FUEL; AVERAGE INTERMEDIATE FLUX IN FUEL TO AVEXAGE THERMAL FLUX IN FUEL VS.

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Reactor Design, Feasability - High Flux Research Reactor


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