
#1
Nov2812, 04:39 PM

P: 495

So CFY gives the average number of atoms of a specific nuclide produced from a fission directly plus that from the decay of precursors, so why does thermal U233 have two values for Gallium @ 7.192x10^(8) and 1.0788x10^(8)? Is this number dependent on the thermal range the neutrons that hit the nucleus of U233?




#2
Nov2812, 06:00 PM

Admin
P: 21,637





#3
Nov2812, 06:21 PM

PF Gold
P: 3,021

For this topic the interest is in thermal neutron fission, i.e. a MSR, just like a light water solid fuel reactor.




#4
Nov2812, 06:40 PM

P: 495

Question about Cumulative Fission Yieldshttp://wwwnds.iaea.org/relnsd/vchart/ I don't understand why there are two values there. I noticed the IAEA definition for CFY's is, "total number of atoms of a specific nuclide produced directly by a fission event and via decay of precursors", (link:http://wwwnds.iaea.org/sgnucdat/safeg2008.pdf) but wikepedia says it is per 100 fissions (link:http://www.nucleonica.net/wiki/index...cts_and_Yields), which is correct? 



#5
Nov2812, 07:12 PM

Admin
P: 21,637

From the JENDL4.0 database (http://wwwndc.jaea.go.jp/cgibin/nuc...0a.cgi?31,72,1) for Ga72 gives:
I added 69 from (http://wwwndc.jaea.go.jp/cgibin/nuc...0a.cgi?31,69,1) and 71 from (http://wwwndc.jaea.go.jp/cgibin/nuc...0a.cgi?31,71,1) 



#6
Nov2812, 07:33 PM

PF Gold
P: 3,021

http://en.wikipedia.org/wiki/Thorium...ctinide_wastes 



#7
Nov2812, 07:57 PM

P: 495

Those values on your table are slightly different from the table I used, should I stick with iaea values or switch to jaea? 


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