[en] A library for shielding analysis has been developed, which is the MATXS-format and has a coupled structure of neutron 175 and gamma 47 groups. The PCA-REPLICA and NESDIP2 benchmarks which simulated LWR pressure vessel, the Winfrith Iron and Iron88 for validation of iron data and the Winfrith Graphite for validation of graphite data have been analyzed with the TRANSX/DANTSYS code systems. The differences between the calculated/measured dosimetry reaction rates are around 15% in the RPV, about 15% in the iron within 50cm thickness and about 10% in the graphite within 60cm thickness. These results are acceptable, considering the standard deviations of the measured data

[en] The scattering laws and MCNP thermal libraries for liquid hydrogen and deuterium are comparatively calculated on HP715 (32-bit computer) and SGI IP27 (64-bit computer) using NJOY97. The results are also compared with the experimental data. In addition, MCNP calculations for the nuclear design of a cold neutron source at HANARO are performed with the newly generated MCNP thermal libraries from two different computers and the results are compared

[en] DPA cross sections of Fe-56 were calculated with the current evaluated nuclear data libraries from ENDF/B-VI, JEF-2.2, JENDL-3.2, BROND-2.2 and CENDL-2.1 using HEATR module of NJOY94.105. The DPA rates were also calculated with the neutron spectra in PWR pressure vessel and the results from each library were intercompared

[en] For various shielding and reactor pressure vessel dosimetry applications, a pseudo-problem-independent neutron-photon coupled MATXS-format library based on the last release of ENDF/B-VI has been generated as a part of the update program for KASHIL-E6, which was based on ENDF/B-VI.5. It has VITAMIN-B6 neutron and photon energy group structures, i.e., 199 groups for neutron and 42 groups for photon. The neutron and photon weighting functions and the Legendre order of scattering are same as KASHIL-E6. The library has been validated through some benchmarks: the PCA-REPLICA and NESDIP-2 experiments for LWR pressure vessel facility benchmark, the Winfrith Iron88 experiment for validation of iron data, and the Winfrith Graphite experiment for validation of graphite data. These calculations were performed by the TRANSXlDANTSYS code system. In addition, the substitutions of the JENDL-3.3 and JEFF-3.0 data for Fe, Cr, Cu and Ni, which are very important nuclides for shielding analyses, were investigated to estimate the effects on the benchmark calculation results

[en] The pseudo fission products for burnup calculations of 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 product data can be used with the KAFAX - F22 or - E66, which are the MATXS-format libraries for analyses of liquid metal fast reactor at KAERI. The 80 groups, MATXS-format libraries of the 172 fission products were generated and burnup chains for generation of the pseudo fission products were prepared