Data from t h e P a c i f i c Northwest L a b o r a t o r y (PNL) andArgonne N a t i o n a l L a b o r a t o r y (ANL) d o s i m e t r y t e s t as a n a l y z e d by P N L , y i e l d t h e r e s u l t of 2 . 1 x 10'' n / c m 2 -s e c f o r t h e t o t a l f l u x l e v e l a t EBR-I1 Row 2 -midplane as measured i n a dosimet r y s t r u c t u r a l subassembly and a t a s t a t e d r e a c t o r power of 50 MW. The v a l u e of 2 . 1 x 1015 n / c m 2 -s e c now a g r e e s t o w i t h i n
~1 0 t o 15% w i t h v a l u e s b a s e d on r e a c t o r p h y s i c s and power cons i d e r a t i o n s and f u e l burnup measurements. P r e v i o u s l y r e p o r t e d l a r g e r d i f f e r e n c e s a r e a t t r i b u t e d mainly t o use of i n c o r r e c t c r o s s s e c t i o n s d a t a and i n t h e s t a t e d v a l u e of low power f o r Run 25a. R e s u l t s from a number of f a s t r e a c t o r t e s t s r e q u i r e a r e d u c t i o n i n p r e v i o u s l y r e p o r t e d EBR-I1 c o r e s p e c t r a l a v e r a g e d c r o s s s e c t i o n v a l u e s of 25% f o r t h e 5 4~e ( n , p ) and 30% f o r 5 8~i ( n , p ) r e a c t i o n t o a c h i e v e c o n s i s t e n c y w i t h r e s u l t s from f i s s i o n r e a c t i o n s .Measured r e a c t i o n r a t e s were u s e d t o g e n e r a t e f l u x -s p e c t r a s o l u t i o n s f o r d i f f e r e n t r a d i a l and a x i a l l o c a t i o n s . For Row 2 -a x i a l l y , f l u x -s p e c t r a l d i f f e r e n c e s were o b s e r v e d between low and h i g h power and between t h e edge and c e n t e r of a s t r u c t u r a l subassembly. I t i s concluded t h a t f i s s i o n and n o n f i s s i o n f l u x m o n i t o r s a r e n e c e s s a r y i n e x p e r im e n t a l s u b a s s e m b l i e s t o s e c u r e a c c u r a t e f l u x and f l u e n c e d a t a f o r m a t e r i a l s i r r a d i a t i o n t e s t s i n EBR-I1 .
A dosimetry flux mappir^ experiment was performed in the EBR-II reactor during Run 75D. Fission and reaction rate data were analyzed from 54 flux spectral sets, containing up to 18 dosimeters and numerous interspersed Fe gradient wires, located in six subassemblies from Row 2 out through Row 8. The dosimeters were located axially from 70 cm belcw to 75 cm above reactor midplane. The fission and reaction rate data were used to generate neutron spectra from which r,z matrices of nuclear parameters were generated. This report includes parameter matrices for total flux, flux with E>0.1 MeV, neutron average energy (£), and atom displacement cross section values for stainless steel.
It has been reproduced fro18 the best avsllable copy to permit the broadest possilrla availability. Pub1 i c a t i o n : GEND-EPRI-NRC HANFORD ENGINEERING DEVELOPMENT LABORATORY Operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corporation, under the Department of Energy Conbact No. DE
A dosimetry q e r i m e n t has been designed and fabricated for incZusion i n the EqerirnentaZ Breeder Reactor-11 (EBR-II) during Run 97 i n a Rm 2 position. V d o u s types of dosimeter materia2 have been inc2uded i n the sing2e B-7c p i n from 60 cm beZm mic@Zane t o 60 cm above. This report contains the as-buitt description of irradiation harcbare and a detai2ed description of the dosimetry.
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