International Reactor Dosimetry File 2002 - IAEA Publications

TABLE 6.2. CROSS-SECTIONS IN IRDF-2002 AND THEIR CHARACTERISTICS (TEMPERATURE OF 300 K) (cont.)
Reaction
Selected
evaluation
Calculated
library crosssection
(2200 m/s)
σ L (b)
Resonance
integral from
library data
IR L (b)
Uncertainty in
library data
Thermal
(%)
Epithermal
(%)
Calculated average
library crosssection
in 252 Uncertainty in
Cf
(%) a C/E
fission (mb) a
241 Am(n,f) JENDL/D-99 3.03 7.84 2.00 1.56 1396 2.81 (2.90) Thermal: 0.99 ± 0.004
b
Epithermal: no
experimental data
No experimental data in
252 Cf fission field
Calculated and experimental data for the response of the activation detectors in the neutron field of the 252 Cf spontaneous fission are from
Mannhart (see Section 4).
a
b
Evaluated experimental data from Ref. [6.9].
Diagonal matrix.
c
d
Evaluated experimental data from Ref. [6.10].
e
Sum of cross-sections of (n,np)+(n,pn)+(n,d) reactions.
Metastable state of the product nucleus.
g
Unreliable uncertainty (corresponding data have been withdrawn from ENDF/B-VI).
(u): Updated data.
(n): New data.
Notes: Column 8 shows the contribution of the energy dependent library cross-section data to the uncertainty of ; values in brackets give the
total standard deviation of , including the contribution of the uncertainty of the 252 Cf spectrum function. Uncertainties given for the
C/E values involve the standard deviations of both the calculated and experimental cross-section data. All uncertainty data in the table are
expressed in terms of one standard deviation.
f
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