IAEA Handbook of Nuclear Data for Safeguards 
Interactive chart of nuclides | A-6. Average number of neutrons emitted per fission |
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| Nuclide |
Type |
Total-neutron Yield | Delayed-neutron Yield | ||||||||
| νt |
Source |
νd |
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| fast = fast spectrum, thermal = thermal spectrum, spontaneous = spontaneous fission. |
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| References |
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| IAEA-CRP-STD |
S. A. Badikov, C. Zhenpeng, A. D. Carlson, E. V. Gai, G. M. Hale, F.-J. Hambsh, H. M. Hofmann, T. Kawano, N. M. Larson, V. G. Pronyaev, D.L. Smith, Soo-Youl Ho, S. Tagesen, H. K. Vonach, H.L. Nichols, IAEA CRP "International Evaluation of Neutron Cross-Section Standards", IAEA Scientific and Technical Report STI/PUB/1292, November 2007, International Atomic Energy Agency, Vienna, Austria, ISBN 90-0-100807-4. http://www-nds.iaea.org/standards/. |
ENDF/B-VII |
U.S. Evaluated Nuclear Data Library ENDF/B-VII β1, http://www.nndc.bnl.gov/exfor/endf00.htm, 3 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. |
JEFF-3.1 |
Joint Evaluated Fission and Fusion File, Incident-neutron data, http://www-nds.iaea.org/exfor/endf00.htm, 26 February 2006; see also A. Koning, R. Forrest, M. Kellett, R. Mills, H. Henriksson, Y. Rugama, The JEFF-3.1 Nuclear Data Library, JEFF Report 21, OECD/NEA, Paris, France, 2006, ISBN 92-64-02314-3. |
NEA/WPEC-6 |
G. Rudstam, Ph. Finck, A. Filip, A. D'Angelo, R.D. McKnight, Delayed Neutron Data for the Major Actinides, Volume 6, NEA/WPEC-6, NEA/OECD, Paris, France, 2002. |
EXFOR |
Experimental Nuclear Reaction Data http://www-nds.iaea.org/exfor/exfor00.htm, 27 March 2006. |
P&I(1998) |
V. M. Piksaikin, S. G. Isaev, Correlation properties of delayed neutrons from fast neutron induced fission, pp. 1-13 in INDC(CCP)-415, October 1998, IAEA, Vienna, Austria. |
Mills(1995) |
R. W. Mills, Fission product yield evaluation, PhD thesis, University of Birmingham, UK, March 1995. |
Tuttle(1979) |
R. J. Tuttle, Delayed-neutron yields in nuclear fission, pp. 29-67 in Proc. Consultants' Meeting on Delayed Neutron Properties, 26-30 March 1979, INDC(NDS)-107 (1979) 29, IAEA, Vienna, Austria. |
| Notes |
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(1) Uncertainties estimated from selected experimental data reported by P&I (1998). (2) Uncertainties estimated from selected experimental data available in EXFOR. (3) Delayed-neutron data adopted from NEA/WPEC-6. (4) Prompt-neutron yield adopted from ENDF/B-VII β3; uncertainty in prompt-neutron yield estimated from the U-238 covariance files included in the ENDF/B-VII β1 library (modification flag 5E for material 9237); total neutron yield calculated as the sum of prompt- and delayed-neutron yields. (5) Prompt-neutron yield adopted from the JEFF-3.1 radioactive decay data library; uncertainty in prompt-neutron yield estimated from selected experimental data available in EXFOR; total spontaneous neutron yield calculated as the sum of prompt- and delayed-neutron yields. |
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