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A Nuclear Cross Section Data Handbook

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●la9tk<br />

(Il,2n)<br />

(18,h)<br />

(n,n’c)<br />

(m,~)<br />

Average Fission Product from 235U<br />

ZAID=45117.90C<br />

SOURCE:Group T-2 (MAT=998, File /077433/AVFISPRO/SIGMA/U235E3)<br />

REFERENCE: “Average Neutronic Properties of “Prompt” Fission Products,”<br />

by D. G. Foster, Jr. and E. D. Arthur<br />

Los Alarnos National Laboratory report LA-9168-MS (February 1982)<br />

Continuous Energy<br />

ZAID=4511 7.90C NES.399 T=30@K<br />

Discrete Reaction A’<br />

ZAID=45117.90D NJ3S=263 T=30@K A<br />

Multigroup<br />

ZAID=45117.90M 30-Group T=30@K i<br />

Abundance: See Appendix A.<br />

Deneity:See Appendix A,<br />

Photon-Production <strong>Data</strong> - Yea<br />

Heating Numbem - Local<br />

Enagy Range -10-11 to 20 MeV<br />

MT E~in(MeV) &~.(MeV) Q~(MeV) QR(MeV)<br />

2 1.0000-11 2. 0000+01<br />

16 3. 6983+00 2. 0000+01 -3. 6666+00 -3. 6666+00<br />

1? 9. 7490+00 2. 0000+01 -9. 6660+00 -9. 6650+00<br />

91 1.6341-01 2.0000+01 -1.5209-01-1.5209-01<br />

102 1.0000-11 2.0000+01 7. 1917+00 7. 1917+00<br />

122<br />

i<br />

\<br />

YERMAL<br />

;: rclvl’=usszsbuwu<br />

M)r ““-%xll!m - “<br />

E=l.oow<br />

SIL3VT = 7.4.? bawu<br />

UFP - 209 m<br />

E=14.00 MeV<br />

SIG7UT = 4.s.9 bw’m<br />

MFP. &.mc?n<br />

.S’L4s&c<br />

lmu p&.49wc<br />

. mm ygAsl’ic

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