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JAERI 1287 JNDC Nuclear Data Library of Fission Products Fir

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16 <strong>JNDC</strong> <strong>Nuclear</strong> <strong>Data</strong> <strong>Library</strong> <strong>of</strong> <strong>Fission</strong> <strong>Products</strong> <strong>JAERI</strong> <strong>1287</strong><br />

as follows:<br />

Zp(A) = Zp(A, Standard) + AZp(Ternary)+dZp(A). (2.4.4)<br />

The first term in the right hand side is the standard value for thermal-neutron fission <strong>of</strong> 23S U<br />

and it is tabulated in Table A-11 <strong>of</strong> Ref. 48. The second term is the correction term for ternary<br />

fission, and the third term is further decomposed into the following three terms.<br />

4Zp(A)=a(Zc-92)+b(Ac~-236)+c(E*-6.52), (2.4.5)<br />

where Zc and Ac are the charge and mass number <strong>of</strong> the compound nucleus, respectively,<br />

and E* is the excitation energy in MeV. The values <strong>of</strong> the coefficients a, b and c were determined<br />

by a least-squares treatment <strong>of</strong> the available fractional chain yield data for spontaneous<br />

and neutron induced fissions 48 ^. Nethaway derived the values,<br />

a = 0.414 ± 0.016 and b = -0.143 ± 0.007 for light fragment products;<br />

a = 0.547 ± 0.010 and b = —0.183 ± 0.004 for heavy fragment products;<br />

a = 0.50 ± 0.03 and b = —0.165 ± 0.02 for valley products.<br />

Mass No.<br />

66- 74<br />

76<br />

78<br />

80<br />

82<br />

84<br />

86<br />

88<br />

90<br />

92<br />

94<br />

96<br />

98<br />

100<br />

102<br />

Table 2.4.3 Values <strong>of</strong> the parameter c for the evaluation <strong>of</strong> the most probable charge<br />

c<br />

0.0200 ±0.0030<br />

0.0200 + 0.0025<br />

0.0200 ±0.0025<br />

0.0200 ±0.0020<br />

0.0200 + 0.0016<br />

0.0200 + 0.0016<br />

0.0200 ±0.0016<br />

0.0196 ±0.0012<br />

0.0189 ±0.0011<br />

0.0181 ±0.0011<br />

0.0171 +0.0010<br />

0.0160 ±0.0010<br />

0.0157 ±0.0009<br />

0.0159 ±0.0013<br />

0.0173 ±0.0017<br />

Mass No.<br />

104<br />

106<br />

108<br />

110<br />

112<br />

114<br />

116<br />

118<br />

120<br />

122<br />

124<br />

126<br />

128<br />

130<br />

132<br />

c<br />

0.0190 ±0.0023<br />

0.0211 ±0.0030<br />

0.0233 ±0.0037<br />

0.0257 ± 0.0046<br />

0.0283 ±0.0057<br />

0.0311 ±0.0062<br />

0.0341 +0.0068<br />

0.0371 +0.0067<br />

0.0402 ± 0.0064<br />

0.0433 ±0.0061<br />

0.0464 ±0.0056<br />

0.0495 ±0.0050<br />

0.0505 ±0.0041<br />

0.0509 ±0.0031<br />

0.0500 + 0.0025<br />

Mass No.<br />

134<br />

136<br />

138<br />

140<br />

142<br />

144<br />

146<br />

148<br />

150<br />

152<br />

154<br />

156<br />

158-172<br />

Table 2.4.4 Correction factor Azp {Ternary) due to ternary<br />

fission 41 ), mass number Ac, and excitation<br />

energy £* (MeV) <strong>of</strong> compound nucleus 48 )<br />

Fissile<br />

235 U(T)<br />

235 U(F)<br />

23S U(H)<br />

238 U (F)<br />

238 U (H)<br />

239 Pu (T)<br />

239 Pu (F)<br />

241 Pu (T)<br />

233 U (T)<br />

232 Th (F)<br />

AZP {Ternary)<br />

0.05062<br />

-0.10021<br />

-0.06241<br />

-0.00860<br />

-0.10089<br />

0.01846<br />

-0.06287<br />

-0.08924<br />

0.03989<br />

0.01299<br />

Zc<br />

92<br />

92<br />

92<br />

92<br />

92<br />

94<br />

94<br />

94<br />

92<br />

90<br />

Ac<br />

236<br />

236<br />

236<br />

239<br />

239<br />

240<br />

240<br />

242<br />

234<br />

233<br />

£*(MeV)<br />

6.52<br />

8.31<br />

21.26<br />

6.57<br />

19.52<br />

6.50<br />

8.30<br />

6.27<br />

6.81<br />

6.56<br />

c<br />

0.0472 ± 0.0024<br />

0.0416 ±0.0021<br />

0.0329 ±0.0016<br />

0.0276 ±0.0014<br />

0.0241 +0.0012<br />

0.0217 ±0.0013<br />

0.0203 +0.0016<br />

0.0195 +0.0019<br />

0.0195 ±0.0023<br />

0.0195 + 0.0027<br />

0.0195 ±0.0031<br />

0.0195 ±0.0035<br />

0.0195 ±0.0039

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