JAEA-Data-Code-2011-025

JAEA-Data/Code 2011-025

Fig. 7.5 Betaand gamma-ray components of 239Pu decay heat after burst fission by thermal neutrons

Fig. 7.6 Total decay heat and uncertainties of the calculated decay heat for 239Pu thermal neutron fission

JAEA-Data/Code 2011-025

Fig. 7.7 Betaand gamma-ray components of 239Pu decay heat after burst fission by fast neutrons

Fig. 7.8 Total decay heat and uncertainties of the calculated decay heat for 239Pu fast neutron fission

JAEA-Data/Code 2011-025

Fig. 7.9 Betaand gamma-ray components of 238U decay heat after burst fission by fast neutrons

Fig. 7.10 Total decay heat and uncertainties of the calculated decay heat for 238U fast neutron fission

JAEA-Data/Code 2011-025

Fig. 7.11 Betaand gamma-ray components of 241Pu decay heat after burst fission by thermal neutrons

Fig. 7.12 Uncertainty of total decay heat calculation for 241Pu thermal neutron fission.

JAEA-Data/Code 2011-025

Fig. 7.13 Betaand gamma-ray components of 232Th decay heat after burst fission by fast neutrons

Fig. 7.14 Total decay heat and uncertainties of the calculated decay heat for 232Th fast neutron fission

JAEA-Data/Code 2011-025

Fig. 7.15 Betaand gamma-ray components of 233U decay heat after burst fission by fast neutrons

Fig. 7.16 Total decay heat and uncertainties of the calculated decay heat for 233U fast neutron fission

JAEA-Data/Code 2011-025

8Summary

JENDL FP Decay Data File 2011 (JENDL/FPD-2011) and JENDL FP Yield File 2011 (JENDL/FPY-2011) were compiled for the calculation of decay heat and nuclides inventories in spent fuel of nuclear reactors. The decay data file contains the data of 1142 unstable nuclides or states (1284 including stable nuclides). The compilation was carried out to keep the consistency between the average beta and gamma decay energy values and their spectral data by adopting the theoretically calculated spectral data for the nuclides with no or doubtful measured data. About 500 nuclides have adopted theoretically calculated spectra.

Recently measured TAGS average decay energy values were adopted in the decay data file.The spectral data of the nuclides adopting TAGS decay energy were derived from the TAGS strength function for the beta-ray spectrum. For the gamma-ray spectra, the ENSDF spectral data were compensated with the theoretical spectrum in order to keep the consistency between the TAGS decay energy and the gamma-ray spectral data.

The fission yield data were compiled based on the ENDF/B-VI yield data with the modification to coincide with the number of nuclides contained in the decay data file. The cumulative yields were calculated based on the decay chains of the JENDL/FPD-2011 file.

Both of the JENDL/FPD-2011 and JENDL/FPY-2011 files were applied to calculate the decay heat of various kinds of fissioning nuclides and the calculated results were compared with the measured decay heat data. The uncertainty of the decay heat calculation was obtained with the method of the sensitivity analysis. The calculated results of the decay heat showed good agreement with the measured data. The uncertainties of the calculated results covered well the measured data points for most of the fissioning nuclides. The good agreement showed validity of the both files for the decay heat calculation. It is expected that they will be used for the calculation of decay heat and nuclide inventories of spent fuel.

Acknowledgements

The author is grateful to the members of “Decay Heat Evaluation Working Group” of Japanese Nuclear Data Committee and members of Nuclear Data Center , JAEA, for the continuous support and encouragement to the present work. He also gives thanks to Dr. M. Ishikawa for his continuous interest in decay heat calculation.

References

1)Tasaka, K. et al., “JNDC nuclear data library of fission products,” Japan Atomic Energy Research Institute, JAERI 1287 (1983). Tasaka, K. et al., “JNDC Nuclear Data Library of Fission Products -Second Version -,” Japan Atomic Energy Research Institute, JAEARI 1320 (1990).

2)Cross Section Evaluation Working Group, “ENDF-6 Formats Manual,” Edited by M. Herman, Brookhaven National Laboratory, BNL-NCS-44945-05-Rev. (2001).

3)Katakura, K. et al., “JENDL FP Decay Data File 2000,” Japan atomic Energy Research Institute, JAERI 1343 (2001).

4)Nuclear Energy Agency (NEA) (2007), “Assessment of Fission Product Decay Data for Decay Heat Calculations,” Vol. 25, International Evaluation Co-operation, A report by the Working Party on International Evaluation Co-operation of the NEA Nuclear Science Committee, NEA/WPEC-25, OECE/NEA, Paris.

5)Algora, A. et al., Phys. Rev. Lett. 105, p.202501 (2010).

JAEA-Data/Code 2011-025

6)Aleklett, K. and Rudstam, G., Nucl. Sci. Eng. 80, p.74 (1982), and references therein.

7)Greenwood, R.C. et al., Nucl. Instrum. Methods Phys. Res. A390, p.95 (1997).

8)Bhat, M.R. “Evaluated Nuclear Structure Data File (ENSDF),” Proc. of International Conference on Nuclear Data for Science and Technology, Springer-Verlag, Berlin, Germany (1992).

9)Burrows, T.W., “The Program RADLST,” BNL-NSC-52142 (1988); The program is downloadable from the web site of NNDC, http://www.nndc.bnl.gov

10)Hardy, J.C. et al., Phys. Lett. 71B, p.307 (1977).

11)Pfeiffer, B. et al., Prog. Nucl. Energy, 41, p.39 (2002).

12)England, T.R. private communication.

13)England, T.R. and Rider, B.F. “Evaluation and Compilation of Fission Product Yields,” Los Alamos National Laboratory, LA-UR-94-3106, ENDF-349 (1994).

14)Madland, D.G. and England, T.R. “Distribution of Independent Fission Product Yields to Isomeric State,” Los Alamos National Laboratory, La-6595-MS (1976).

15)Mills, R.W. “Fission product yield evaluation,” A thesis, University of Birmingham (1995).

16)Audi, G. Private communication (2009).

17)Shibara, K. et al., J. Nucl. Sci. Technol., 48, p.1 (2011).

18)Oyamatu, K., “Easy-to-use Application Programs to Calculate Aggregate Fission-Product Properties on Personal Computers,” Proc. of The 1998 Symposium on Nuclear Data, Japan Atomic Energy Research Institute, JAERI-Conf 99-002, p.234 (1999).

19)England, T.R. et al., “Background Radiation from Fission Pulses,” Los Alamos National Laboratory, LA- 11151-MS (1988).

20)Devillers, C. “The Importance of Fission Product Nuclear Data in Reactor Design and Operation,” IAEA Panel, Petten (1977).

21)Dickens, J.K. et al., “Fission Product Energy Release for Time following Thermal Neutron Fission of 235U between 2 and 14,000 seconds,” Oak Ridge National Laboratory, ORNL/NUREG-14 (1977); J.K. Dickens et al.. Nucl. Sci. Eng., 74, p.106 (1980).

22)Dickens, J.K. et al., “Fission Product Energy Release for Time following Thermal Neutron Fission of 239Pu between 2 and 14,000 seconds,” Oak Ridge National Laboratory, ORNL/NUREG-34 (1978); J.K. Dickens et al.. Nucl. Sci. Eng., 78, p.126 (1981).

23)Dickens, J.K. et al., “Fission Product Energy Release for Time following Thermal Neutron Fission of 241Pu between 2 and 14,000 seconds,” Oak Ridge National Laboratory, NUGEG/CR-0171, ORNL/NUREG-47 (1978)

24)Akiyama, M. et al., J. Atom. Ener. Soc. of Japan, 24, p.709 (1982) [in Japanese].

25)Akiyama, M. et al., ibid., 24, p.803 (1982) [in Japanese].

JAEA-Data/Code 2011-025

26)Akiyama,M. and An, S. “Measurement of fission product decay heat for fast reactor,” Proc. of Int. Conf. on Nucl. Data for Science and Technol., Antwerp, Belgium, p.237 (1982).

27)Johanson, P.-I. “Integral DEtermination of the Beta and Gamma Heat in Thermal-Neutron-Induced Fission of 235U and 239Pu, and of the Gamma Heat in Fast Fission of 238U,” Proc. of Int. Conf. on Nucl. Data for Science and Technol., Mito, Japan, p.257 (1988).

28)Seabury, E.H. et al., “Decay Heat Measurements Following Neutron Fission of 238U,” Proc. Int. Conf. on Nucl. Data for Science and Technol., Trieste, Italy, p.753 (1997).

29)Nguyen, H.V. et al., “Decay Heat Measurements Following Neutron Fission of 235U and 239Pu,” Proc. Int. Conf. on Nucl. Data for Science and Technol., Trieste, Italy, p.835 (1997).