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151 T h e proposed experiments on t h e r e l e a s e and transport of f i s s i o n products from UO, a r e described i n s o n e detail elsewhere.’2 They are s c a l e d a t 1 and 10% of t h e size of t h e L O F T experiment b a s e d upon the m a s s of fuel in t h e L O F T core. T h e fuel in t h e s e experiments i s to b e melted by nuclear self-heating i n a reactor facility using a driver core. T h e s u g g e s t e d f a c i l i t i e s a r e t h e P o w e r Burst F a c i l i t y 1 3 for t h e 1%s c a l e experiment using approximately one L O F T h e 1 element, and t h e L O F T i t s e l f for t h e 10% s c a I e experiment u s i n g approximately five LOFT fuel el em ent s. Alternative experiments at the same scale u s i n g a nonnuclear mef.hod of heating are proposed to fill t h e gap i n s c a l i n g i f for r e a s o n s of e x p e n s e o r scheduling t h e nuclear experiments cannot b e performed. T h e 1%scale experiment i s proposed for t h e Containment Research Installation, and t h e 10% scale experimerit is proposed for t h e Containment Systems Experiment. l 5 An electrical method of heating t h e fuel is proposed, which is presently under development in a n AEC-sponsored pro gram. 1 2 T h e capability’of performing any of t h e proposed experiments a p p e a r s to b e near at hand. All four Eacilities are under construction, and t h e capability

of e l e c t r i c a l heating is being developed. However, three of t h e four p o s s i b l e experiments involve f a c i l i t i e s which a r e already scheduled for experimental programs. T h e s e a r e t h e L,OFT, CSE, and CRI facilities. T h e addition of t h e s e proposed experiments would c a u s e d e l a y s in programs which a r e very much needed i n other p h a s e s of nuclear safety work. T h e remaining facility, t h e P o w e r Burst Facility, which is still to b e constructed, seems t h e most promising. With t h e addition of t h e s e experiments to t h e AEC Nuclear Safety Program, t h e comparison of s i z e o f planned nuclear safety experiments w i l l b e a s shown i n Fig. 16.4. T h e accomplishment of t h e s e experiments w i l l produce a s c a l i n g range which should cover all p o s s i b l e mechanisms of f i s s i o n product behavior and make extrapolation of d a t a from o n e experiment to the other more reliable. 1 3 E . F e i n a u e r and R. S . Kern (eds.), Preliminary Safcly A n a l y s i s Hcporf, Power Bnrst Faczlity, IDO17060 (revised June 1965).

“G. W. Parker and W. J. Martin, “The Containment Research Installation,’’ NtzcJ. S a f e t y Program Semianrl. Progr. RefJt. J u n e 30, 196.5, ORNL-3843, pp. 92-97.

”s. J. Rogers, Program for Corltsinment S y s t e m s Experiment, WW-83607 (September 1964).


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