update 2007/06/02

Proceedings of 2006 Symposium on Nuclear Data

Please refer as:
[author(s) name], "[Paper No.]: [title]", T. Fukahori (Ed.), Proc. of 2006 Symposium on Nuclear Data, Jan. 25-26, 2007, RICOTTI, Tokai-mura, Ibaraki-ken, Japan, ISBN978-4-89047-138-6, Nuclear Data Division, Atomic Energy Society of Japan (2007) [CD-ROM].
Please note "Paper No." is indicated at right side of page bottom in each paper as like SND2006-V.01.

I. Preface

II. Tutorial on Nuclear Data
  1. Use of Covariance Data (in Japanese)
    M. Ishikawa
  2. Use of MVP (in Japanese)
    T. Mori
III. Nuclear Data Needs for Non-energy Applications
  1. Critical Role of Nuclear Data in Nuclear Astrophysics
    Y. Nagai, T. Shima, A. Tomyo, H. Makii, K. Mishima, M. Segawa, H. Ueda, Y. Temma, T. Ohsaki, J. Nishiyama, M. Igashira
  2. Cosmic-ray Transport Simulation in the Atmosphere
    T. Sato, K. Niita
  3. Nuclear Data Relevant to Single Event Upsets in Semiconductor Memories Induced by Cosmic-ray Neutrons and Protons
    Y. Watanabe
IV. Nuclear Data Requirements from Core Design
  1. Nuclear Data Needs for Fast Reactors
    G. Chiba
  2. Nuclear Data Needs for Advanced Reactors
    T. Yoshida
  3. Needs of Nuclear Data for Advanced Light Water Reactor
    M. Chaki
V. Poster Presentations
  1. Recent Activities for MA Cross-Section Measurements (Appendix)
    S. Nakamura, M. Ohta, H. Harada, T. Fujii, H. Yamana
  2. Measurement of Neutron Capture Cross Sections of 139La, 152Sm and 191,193Ir at 55 and 144keV
    Vuong Huu Tan, Tran Tuan Anh, Nguyen Canh Hai, Pham Ngoc Son, T. Fukahori
  3. Measurement of Charged-particle Emission DDX for Carbon with 14-MeV Incident Neutrons
    K. Kondo, I. Murata, K. Ochiai, H. Miyamaru, N. Kubota, C. Konno, T. Nishitani
  4. Measurement of natZr (n,2n) Reaction Cross Section from the Angle Correlated Neutron Spectrum with Pencil-beam DT Neutron Source
    K. Shiken, S. Takaki, K. Kondo, M. Matsunaka H. Miyamaru, I. Murata, K.Ochiai, C.konno, T. Nishitani
  5. Neutron-Production Double-Differential Cross Sections for 150 MeV Neutron-Incidence on Fe
    H. Arakawa, T. Kajimoto, S. Noda, T. Watanabe, N. Shigyo, K. Ishibashi, S. Kunieda, R.C. Haight
  6. Calculation of Fission Yield by Macroscopic-Microscopic Method Based on Selective Channel Scission Model
    M. Ohta, S. Nakamura
  7. Effect of Effective Interaction Potentials Used in Quantum Molecular Dynamics on Nucleon-induced Reactions
    D.N. Kadrev, Y. Watanabe
  8. Nuclear Data Evaluation of 206Pb for Proton- and Neutron-induced Reaction in Energy Region from 20 to 200 MeV
    T. Kajimoto, N. Shigyo, K. Ishibashi, S. Kunieda, T. Fukahori
  9. Prompt Time Constants of a Reflected Reactor
    T. Ye, C. Chen, W. Sun, B. Zhang, D. Tian
  10. Design of MA-loaded Core Experiments Using J-PARC
    T. Sugawara, K. Sugino, T. Sasa
  11. Analyses of Benchmark Experiments at FNS with Recent Nuclear Data Libraries
    K. Ochiai, S. Sato, M. Wada, C. Konno
  12. Development of Burn-up Calculation System for Fusin-fission Hybrid Reactor
    M. Matsunaka, S. Shido, K. Kondo, H. Miyamaru, I. Murata
  13. Nuclear Heating Calculation for the High Flux Test Module in IFMIF
    D. Kaku, T. Ye, Y. Watanabe
  14. Sensitivity Analysis of Actinide Decay Heat Focused on Mixed Oxide Fuel
    N. Hagura, T. Yoshida
  15. Neutron Multigroup Constant Sets of Moderator Materials for Design of Low-Energy Neutron Sources
    Y. Abe, N. Morishima
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