MARC

LEADER 00000nam a22000003u 4500
001 b6002625
003 CoU
005 20151204003304.7
006 m o d f
007 cr |||||||||||
008 160906e19830101||| o| f1|||||eng|d
035 |a (TOE)ost5799158 
035 |a (TOE)5799158 
040 |a TOE  |c TOE 
049 |a GDWR 
072 7 |a 12  |2 edbsc 
072 7 |a 37  |2 edbsc 
086 0 |a E 1.99: conf-830709-26 
086 0 |a E 1.99:la-ur-83-1931 
086 0 |a E 1.99: conf-830709-26 
088 |a conf-830709-26 
088 |a la-ur-83-1931 
245 0 0 |a Multi-isotopic gamma-ray assay system for alpha-contaminated waste  |h [electronic resource] 
260 |a Los Alamos, N.M. :  |b Los Alamos National Laboratory ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1983. 
300 |a Pages: 6 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through SciTech Connect. 
500 |a 01/01/1983. 
500 |a "la-ur-83-1931" 
500 |a " conf-830709-26" 
500 |a "DE83015254" 
500 |a 24. annual meeting of the Institute of Nuclear Materials Management, Vail, CO, USA, 10 Jul 1983. 
500 |a Close, D.A.; Kunz, W.E.; Caldwell, J.T.; Pratt, J.C.; Haff, K.W.; Schultz, F.J. 
520 3 |a The capability of an existing segmented gamma-ray system is being expanded for the analysis of alpha-contaminated waste drums. A cursory assay of 114 transuranic waste drums of 208-l capacity has been made. Analysis of these data indicates a detection limit better than 100 nCi/g of waste for /sup 237/Np//sup 233/Pa, /sup 239/Pu, /sup 241/Am, /sup 243/Am//sup 239/Np, /sup 60/Co, /sup 125/Sb, /sup 134/ /sup 137/Cs, and /sup 154/Eu. A pending Code of Federal Regulation (10CFR61) stipulates that the nuclear industry quantify not only its transuranic waste, but also certain beta- and gamma-ray-emitting fission products. An assay system based on gamma-ray spectroscopy is the only system that can meet this requirement for the fission products. 
536 |b W-7405-ENG-36. 
650 7 |a Alpha-Bearing Wastes.  |2 local. 
650 7 |a Radiometric Analysis.  |2 local. 
650 7 |a Containers.  |2 local. 
650 7 |a Gamma Detection.  |2 local. 
650 7 |a Gamma Spectroscopy.  |2 local. 
650 7 |a Chemical Analysis.  |2 local. 
650 7 |a Detection.  |2 local. 
650 7 |a Materials.  |2 local. 
650 7 |a Quantitative Chemical Analysis.  |2 local. 
650 7 |a Radiation Detection.  |2 local. 
650 7 |a Radioactive Materials.  |2 local. 
650 7 |a Radioactive Wastes.  |2 local. 
650 7 |a Spectroscopy.  |2 local. 
650 7 |a Wastes.  |2 local. 
650 7 |a Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities.  |2 edbsc. 
650 7 |a Inorganic, Organic, Physical And Analytical Chemistry.  |2 edbsc. 
710 2 |a Los Alamos National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
856 4 0 |u http://www.osti.gov/scitech/biblio/5799158  |z Online Access 
907 |a .b6002625x  |b 03-06-23  |c 05-30-10 
998 |a web  |b 09-09-16  |c f  |d m   |e p  |f eng  |g    |h 0  |i 3 
956 |a Information bridge 
999 f f |i b1520e0a-27b8-5980-bfc8-f361ef4cb5e5  |s 0cc861ae-58c5-5e7c-8bd0-ca9c60874601 
952 f f |p Can circulate  |a University of Colorado Boulder  |b Online  |c Online  |d Online  |e E 1.99: conf-830709-26  |h Superintendent of Documents classification  |i web  |n 1