Analysis of Core Physics Experiments of High Moderation Full MOX LWR

The 2003-2004 activity of Reactor Integral Test WG under Subcommittee on Reactor Constants of Japanese Nuclear Data Committee will be presented. During this period, the WG carried out integral tests of JENDL-3.3, ENDF/B-VI and JEFF 3.0 for reactor applications. Some results of integral tests for other latest libraries, JEFF-3.1, ENDF/B-VII, etc. will be also presented. Nuclear Data Library in Design Calculation Go HIRANO TEPSYS, 2-37-28 Reitai, Koto-ku, Tokyo, 135-0034 Japan The characteristics of the lattice codes used for the core design calculation of light-water reactors in Japan are reported from the viewpoint of nuclear data library. At the time of the light-water reactor introduced into Japan, various technologies including the lattice code were also introduced from the nuclear fuel vender such as W.H. or GE. Those lattice codes are based on ENDF/B-4/5 library. They have been constantly improved, and are widely used for the commercial core design. Decades have passed since the introduction of initial lattice codes, and domestic venders are currently developing next generation's lattice codes. Some domestic venders have started employing JENDL series (3.2/3.3) as one of the main nuclide data besides ENDF series. Besides the nuclear data library, the current methodologies of energy groups and resonance calculation will also be reported. Present Status of CENDL Project Yu Hongwei China Nuclear Data Center China Institute of Atomic Energy Chinese Nuclear Data Committee assumes responsibility the management of CENDL project. CENDL is carried out by China Nuclear Data Center and China Nuclear Data Network. From 1996 to 2001, we have completed the evaluation of CENDL-3.0, total 209 nuclides are include CENDL-3.0. The fission product nuclide file of CENDL-3 has been officially released on October 6, 2001, the other file of CENDL-3.0 have been tested and improved for the problems found in the test within china. The next release version of CENDL is CENDL-3.1 library. The evaluation for special purpose file was continued . In order to satisfy the need of ADS project of China, a code MEND for calculating the nuclear data in medium energy region has been developed, some nuclear data have been calculated and