[en] MCNP4C, WIMSD-5, HELIOS libraries are constantly being updated and upgraded by responding users' demands, such as adding new nuclides and burnup chains. Libraries for SFR and VHTR are also being upgraded, and the structure of the group constant is being revised according to the users' needs. Neutron data of 32 fission products were fully evaluated and registered in the ENDF/B-VII.0 which was officially released December 2006 by the Cross Section Evaluation Working Group(CSEWG), USA. Neutron-induced gamma spectra, which are essential in the fields of nuclear industry and space engineering, are newly evaluated for ⁹Y, ⁹³Nb, ¹²⁷I, ¹³³Cs, ¹⁴¹Pr, ¹⁹⁷Au, ^natTl and ²⁰⁹Bi by introducing improved gamma strength function to describe irregular bumps. Various libraries such as for MCNP4C code, WIMSD-5 code, fast reactor, shielding, fission product burnup, and reactor benchmark were generated based on the ENDF/B-VII.0 and JEFF-3.1. Various sensitivity calculations for U-235 and U-238 based on the ENDF/B-VII.0 were carried out and their impacts on the criticalities of a number of international benchmark problems. Neutron capture cross sections of four isotopes, ^{155,156,157,158}Gd were measured using Pelletron accelerator in the TIT of Japan. Upgrade was made on PAL facilities, and measurements were performed for neutron total cross sections for energies from thermal to hundreds eV for Pr