Comparisons of Neutron Cross Sections and Isotopic Composition Calculations for Fission-Product Evaluations

Do Heon Kim; Choong-Sup Gil; Jonghwa Chang; Yong-Deok Lee
May 2005
AIP Conference Proceedings;2005, Vol. 769 Issue 1, p511
Conference Proceeding
The neutron absorption cross sections for 18 fission products evaluated within the framework of the KAERI (Korea Atomic Energy Research Institute)-BNL (Brookhaven National Laboratory) international collaboration have been compared with ENDF/B-VI.7. Also, the influence of the new evaluations on the isotopic composition calculations of the fission products has been estimated through the OECD/NEA burnup credit criticality benchmarks (Phase 1B) and the LWR/Pu recycling benchmarks. These calculations were performed by WIMSD-5B with the 69-group libraries prepared from three evaluated nuclear data libraries: ENDF/B-VI.7, ENDF/B-VI.8 including the new evaluations in the resonance region covering the thermal region, and the expected ENDF/B-VII including those in the upper resonance region up to 20 MeV. For Xe-131, the composition calculated with ENDF/B-VI.8 shows a maximum difference of 5.02% compared to ENDF/B-VI.7. However, the isotopic compositions of all the fission products calculated with the expected ENDF/B-VII show no differences when compared to ENDF/B-VI.7 for the thermal reactor benchmark cases. © 2005 American Institute of Physics


Related Articles

  • Neutron emission in fission of 252Cf(sf). Zeynalov, Sh.; Hambsch, F.-J.; Oberstedt, S.; Fabry, I. // AIP Conference Proceedings;10/15/2009, Vol. 1175 Issue 1, p359 

    The prompt neutron emission in spontaneous fission of 252Cf has been investigated applying digital signal electronics. The goal was to compare the results of this digital data acquisition and digital signal processing analysis to the results of the pioneering work of Budtz-Jo\rgensen and...

  • Group Constants Generation of the Pseudo Fission Products for Fast Reactor Burnup Calculations. Choong-Sup Gil; Do Heon Kim; Jonghwa Chang // AIP Conference Proceedings;2005, Vol. 769 Issue 1, p527 

    The pseudo fission products for the burnup calculations of the liquid metal fast reactor were generated. The cross-section data and fission product yield data of ENDF/B-VI were used for the pseudo fission product data of U-235, U-238, Pu-239, Pu-240, Pu-241, and Pu-242. The pseudo fission...

  • Fission Products Evaluation for the Selected Nuclei. Lee, Y. D.; Chang, J. H. // AIP Conference Proceedings;2005, Vol. 769 Issue 1, p378 

    The neutron cross sections of 19 selected high-priority nuclei were evaluated in the fast energy region. The calculation was compared with the CSISRS experimental data and the ENDF files. Evaluation procedures included an optical-model parameter search, followed by complete nuclear reaction...

  • Use of Integral Data to Improve the European Activation File. Forrest, R. A.; Bém, P.; Kopecky, J.; von Möllendorff, U.; Pillon, M.; Seidel, K.; Simakov, S. P.; Sublet, J.-Ch. // AIP Conference Proceedings;2005, Vol. 769 Issue 1, p515 

    The European Activation File is the source of nuclear data for fusion activation calculations that has been developed in Europe. In order to trust the calculations made with the data, validation is essential. A key part of this is the comparison of the EAF data with integral experiments made in...

  • Distribution of Prompt Neutron Emission Probability for Fission Fragments in Spontaneous Fission of 252Cf and 244,248Cm. Vorobyev, A. S.; Dushin, V. N.; Hambsch, F.-J.; Jakovlev, V. A.; Kalinin, V. A.; Laptev, A. B.; Petrov, B. F.; Shcherbakov, O. A. // AIP Conference Proceedings;2005, Vol. 769 Issue 1, p613 

    Neutrons emitted in fission events were measured separately for each complementary fragment in correlation with fission fragment energies. Two high-efficiency Gd-loaded liquid scintillator tanks were used for neutron registration. Fission fragment energies were measured using a twin Frisch...

  • Landau-Zener effect in the Th neutron-induced fission cross section. Mirea, M.; Tassan-Got, L. // AIP Conference Proceedings;10/15/2009, Vol. 1175 Issue 1, p219 

    The fine structure in the Th neutron induced fission cross section is analyzed in terms of the Landau Zener effect. An excellent agreement with experimental data was obtained. It was shown that the fine structure can be explained by the promotion of the unpaired neutron from one single-particle...

  • Influence of fission fragment excitation energy on prompt fission neutron observables. Lemaire, S.; Talou, P.; Kawano, T.; Chadwick, M. B.; Madland, D. G. // AIP Conference Proceedings;2005, Vol. 798 Issue 1, p213 

    We have implemented a Monte-Carlo simulation of the statistical decay of fission fragments by sequential neutron emission. In this presentation, we report on some numerical results obtained for the spontaneous fission of 252Cf and neutron-induced fission of 235U at 0.53 MeV neutron energy, and...

  • The microscopic theory of fission. Younes, W.; Gogny, D. // AIP Conference Proceedings;10/15/2009, Vol. 1175 Issue 1, p3 

    Fission-fragment properties have been calculated for thermal neutron-induced fission on a 239Pu target, using constrained Hartree-Fock-Bogoliubov calculations with a finite-range effective interaction. A quantitative criterion based on the interaction energy between the nascent fragments is...

  • Neutron induced reactions at the Athens Tandem Accelerator of NCSR “Demokritos”. Vlastou, R.; Papadopoulos, C. T.; Kokkoris, M.; Perdikakis, G.; Galanopoulos, S.; Serris, M.; Giantsoudi, D.; Kossionides, S.; Harissopulos, S.; Karamanis, D.; Assimakopoulos, P. A. // AIP Conference Proceedings;2006, Vol. 831 Issue 1, p181 

    In the 5.5 MV tandem T11/25 Accelerator Laboratory of NCSR “Demokritos” monoenergetic neutron beams have been used in the energy range 7–11.5 MeV, produced via the 2H(d,n) reaction. The flux variation of the neutron beam is monitored by using a BF3 detector, while an...


Read the Article

Courtesy of

Sorry, but this item is not currently available from your library.

Try another library?
Sign out of this library

Other Topics