B-4. Fission product data: Thermal neutron cross sections, resonance integrals, and Westcott factors
Nuclide	Type	Cross Section   σx [barn]	Westcott Factor   g	Resonance Integral   RI [barn]	Source
36-Kr-82	σγ	19 ± 4	1.0004	156 ± 20	[1]
36-Kr-83	σγ	197 ± 10	0.9979	157 ± 25	[1]
36-Kr-84	σγ   σγ(g)   σγ(m)	0.110 ± 0.015   0.042 ± 0.004   0.090 ± 0.013	1.0004	2.43 ± 0.20	[1]
36-Kr-85	σγ	1.66 ± 0.20	0.9996	1.8 ± 1.0	[1]
38-Sr-90	σ0γ	0.0104 ± 0.0014	1.000	0.104 ± 0.016	[1]
40-Zr-90	σγ	0.077 ± 0.016	1.0003	0.17 ± 0.02	[1]
40-Zr-91	σγ	0.83 ± 0.08	1.0003	5.76 ± 0.40	[1]
40-Zr-92	σγ	0.26 ± 0.08	1.0004	0.64 ± 0.11	[2]
40-Zr-93	σγ	0.696	1.0007	17.8	[3]
40-Zr-94	σγ	0.0494 ± 0.0017	1.0004	0.280 ± 0.010	[1]
40-Zr-95	σ0γ	1.2	1.0004	7.79	[4]
40-Zr-96	σγ	0.0229 ± 0.0010	1.0006	5.28 ± 0.11	[1]
41-Nb-94	σ0γ	14.9 ± 1.0	0.999	125 ± 8	[1]
42-Mo-100	σγ	0.199 ± 0.003	1.0003	3.76 ± 0.15	[1]
42-Mo-95	σγ	13.4 ± 0.3	1.0000	118 ± 7	[1]
42-Mo-96	σγ	0.5 ± 0.2	1.0006	17 ± 3	[1]
42-Mo-97	σγ	2.2 ± 0.2	1.0001	14.4 ± 3.0	[1]
42-Mo-98	σ0γ	0.130 ± 0.006	1.0008	6.7 ± 0.3	[1]
43-Tc-99	σ0γ	22.8 ± 1.3	1.004	358 ± 20	[1]
44-Ru-100	σ0γ	5.8 ± 0.4	1.0003	11.2 ± 1.1	[1]
44-Ru-101	σ0γ	5.2 ± 0.3	1.0011	102 ± 10	[1]
44-Ru-102	σ0γ	1.27 ± 0.04	1.0003	4.9 ± 0.3	[1]
44-Ru-103	σγ	1.2	1.0017	47	[5]
44-Ru-104	σ0γ	0.491 ± 0.010	1.0004	6.3 ± 0.2	[1]
44-Ru-106	σ0γ	0.146 ± 0.045	1.0004	2.0 ± 0.6	[1]
51-Sb-124	σ0γ	17.4 ± 2.8	1.000	156	[6]
53-I-129	σ0γ	30.3 ± 1.2	0.998	33.8 ± 1.4	[1]
54-Xe-130	σ0γ   σ0γ(m)	4.8 ± 1.2   0.45 ± 0.10	0.9984	4.8	[7]
54-Xe-131	σ0γ	87 ± 10	1.0015	890 ± 50	[1]
54-Xe-132	σ0γ   σ0γ(m)	0.45 ± 0.06   0.05 ± 0.01	1.0004	5.0 ± 0.6   0.9 ± 0.2	[1]
54-Xe-133	σrγ	190 ± 90	1.0004	90	[6]
54-Xe-135	σ0γ	2650000 ± 110000	1.1594	7600 ± 500	[1]
54-Xe-136	σ0γ	0.26 ± 0.02	1.0007	0.74 ± 0.21	[8]
55-Cs-133	σ0γ   σ0γ(m)	30.3 ± 1.1   2.6 ± 0.1	1.0029	437 ± 26   29.0 ± 1.1	[1]
55-Cs-134	σrγ	140 ± 12	0.9985	105	[9]
55-Cs-135	σγ	8.3 ± 0.3	0.9977	37.9 ± 2.7	[10]
55-Cs-137	σrγ	0.27 ± 0.03	1.0005	0.35	[11]
58-Ce-144	σγ	1.0 ± 0.1	1.0005	2.6 ± 0.3	[1]
59-Pr-141	σ0γ   σ0γ(m)	11.5 ± 0.3   3.9 ± 0.3	0.9996	17.4 ± 2.0	[1]
59-Pr-143	σ0γ	90 ± 10	0.9998	190 ± 25	[1]
60-Nd-142	σγ	18.7 ± 0.7	0.9990	6.2	[12]
60-Nd-143	σ0γ	325 ± 10	0.9967	129 ± 30	[1]
60-Nd-144	σγ	3.6 ± 0.3	1.0004	4.2 ± 0.5	[1]
60-Nd-145	σ0γ	50.0 ± 1.0	1.0001	230 ± 35	[1]
60-Nd-146	σ0γ	1.49 ± 0.06	1.0004	2.57 ± 0.14	[1]
60-Nd-147	σγ	440 ± 150	0.9957	539.8	[13]
60-Nd-148	σ0γ	2.58 ± 0.07	1.0005	15.5 ± 1.5	[1]
60-Nd-150	σ0γ	1.04 ± 0.04	1.0003	15.2 ± 0.8	[1]
61-Pm-147	σ0γ   σ0γ(g)   σ0γ(m)	168.4 ± 3.5   96.0 ± 1.8   72.4 ± 3.0	0.9971	2064 ± 100   1274 ± 66   790 ± 100	[1]
61-Pm-148	σrγ	2000 ± 1000	1.0005	2515	[14]

 

Notation
σ0	Neutron cross section at 2200 m/s.
σ	Neutron cross section measured in a Maxwellian spectrum.
σr	Neutron cross section measured with reactor neutrons.
σc	Neutron cross section calculated from resonance parameters or derived from equivalent data of the natural element.
σ(m)	Neutron cross section leading to a metastable state of the product.
σ(g)	Neutron cross section leading to the ground state of the product.
g	Westcott factor: ratio of the Maxwellian averaged cross section σ to 2200 m/s cross section σ0 (g = σ/σ0 ). If the cross section varies as a function of 1/v, g = 1.0.
RI	Infinite dilution resonance integral (including the 1/v contribution).
γ	Subscript for radiative capture cross section.
f	Subscript for fission cross section.

 

References
ANR	S. F. Mughabghab, Atlas of Neutron Resonances, Resonance Parameters and Thermal Cross Sections, Z = 1 - 100, 5th Edition, Elsevier, Amsterdam, 2006.
ENDF/B-VII	U.S. Evaluated Nuclear Data Library ENDF/B-VII β1, http://www.nndc.bnl.gov/exfor7/endf00.htm, 2 October 2006; see also M. B. Chadwick et al., ENDF/B-VII.0 : Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology, Nucl. Data Sheets 107 (2006) 2931.
JENDL-3.3	Japanese Evaluated Nuclear Data Library, Incident-neutron data, http://www-nds.iaea.org/exfor/endf00.htm, 2 October 2006.
HAR-91	H. Harada, et al., Proceedings of the 1990 Symposium on Nuclear Data, , Japan Atomic Energy Research Institute report JAERI-M 91-032 (1991) 199.
GRY-87	G. Gryntakis et al., Handbook on Nuclear Activation Data, IAEA Technical Reports Series No. 273 (1987) 199.
SEK-87	T. Sekine et al., Triple Neutron Capture of 153Eu in a Reactor: the Cross Sections of 154Eu and 155Eu, Appl. Radiat. Isot. 38 (1987) 513.

 

Notes   [1] Cross-section data and resonance integral adopted from ANR; Westcott factor calculated from the ENDF/B-VII library. [2] Cross-section data adopted from ANR; value of the resonance integral adopted from ANR; RI uncertainty adopted from GRY-87; Westcott factor calculated from the ENDF/B-VII library. [3] Data adopted from ENDF/B-VII; σγ < 4 barns and RI = 17.5 barns are reported in ANR; σγ = 2.24 barns and RI = 18.2 barns are reported in JENDL-3.3. [4] Data adopted from the ENDF/B-VII library; ENDF/B-VII data were adopted from JENDL-3.3; no data available in ANR. [5] Data adopted from the ENDF/B-VII library; values in ANR are 1.2 and 5 barns for the thermal cross section and resonance integral, respectively; no uncertainty was reported. [6] Cross-section data adopted from ANR; resonance integral and Westcott factor calculated from the ENDF/B-VII library; resonance integral not reported in ANR. [7] Cross-section data and resonance integral adopted from ANR; RI uncertainty not available; Westcott factor calculated from the ENDF/B-VII library. [8] Cross-section data and resonance integral adopted from ANR; Westcott factor calculated from the ENDF/B-VII library; RI = 0.14 ± 0.01 barns from resolved resonance parameters. [9] Cross-section data adopted from ANR; resonance integral and Westcott factor calculated from the ENDF/B-VII library; RI = 76 barns is reported in ANR from the resolved resonance parameters. [10] Cross-section data and resonance integral adopted from ANR; Westcott factor calculated from the ENDF/B-VII library; RI = 50.9 barns in the ENDF/B-VII library. [11] Cross-section data adopted from ANR; resonance integral and Westcott factor calculated from the ENDF/B-VII library; measured RI = 0.35 ± 0.07 barns reported by HAR-91. [12] Cross-section data adopted from ANR; resonance integral and Westcott factor calculated from the ENDF/B-VII library; values of 34 ± 11 and 8.8 ± 0.5 barns are also reported in ANR - the first is an experimental value and the second was calculated from the resolved resonance parameters; the ENDF/B-VII evaluation is in good agreement with recent measurements of the capture cross section in the energy range between 3 and 225 keV. [13] Cross-section data adopted from ANR; resonance integral and Westcott factor calculated from the ENDF/B-VII library; a resonace integral of 430 barns was calculated from the resolved resonance parameters, and is reported in ANR. [14] Cross-section data adopted from ANR; resonance integral and Westcott factor calculated from the ENDF/B-VII library; resonance integrals are not reported in ANR. [15] Data adopted from the ENDF/B-VII library; an upper limit of 700 barns is reported for σγ in ANR. [16] Data adopted from ANR; resonance integral calculated from resolved resonance parameters; a resonance integral of 3700 ± 400 barns is reported by GRY-87. [17] All data adopted from ANR. [18] Cross-section data adopted from ANR; Westcott factor and resonance integral calculated from the ENDF/B-VII library; a resonance integral of 3700 ± 2000 barns is reported by GRY-87. [19] All data adopted from ANR; resonance integral is not available for the Eu-151(n,γ)Eu-152m2 reaction. [20] Cross-section data and Westcott factor taken from ANR; resonance integral calculated from the ENDF/B-VII library; a value of 2170 barns is reported in JENDL-3.3 for the resonance integral. [21] Cross-section data taken from ANR; Westcott factor calculated from the ENDF/B-VII library, a value of g = 0.8979 is reported in ANR; resonance integral adopted from the ENDF/B-VII library, while a value of 1500 ± 450 barns is reported by GRY-87. [22] Cross-section data taken from ANR; resonance integral and Westcott factor calculated from the ENDF/B-VII library; resonance integral in the ENDF/B-VII library is in good agreement with the value of 15300 ± 2700 barns reported by SEK-91; a resonance integral of 23200 ± 300 barns is reported in ANR. Read our Disclaimer Copyright International Atomic Energy Agency - Nuclear Data Section P.O. Box 100, Wagramer Strasse 5, A-1400 Vienna, Austria Telephone (+431) 2600-0; Facsimilie (+431) 2600-7; E-mail: nds.contact-point@iaea.org