Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 235 U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

The revision work of JENDL-3 has been made by considering feedback information of various benchmark test,s. The main revised quantities are the resonance parameters, capture and inelastic scattering cross sections, and fission spectra of main actinide nuclides, the total and inelastic scattering cross sections of structural materials, the resonance parameters the capture and inelastic scattering cross sections of fission products, and the y-ray production data. The revised data were released as JENDG3.2 in June 1994. The preliminary benchmark tests indicate thar JENDG3.2 predicts various reactor characteristics more successfully than the previous versioli of JENDL-3.1.

Evaluation for JENDL-3.3 has been performed by considering the accumulated feedback information and various benchmark tests of the previous library JENDL-3.2. The major problems of the JENDL-3.2 data were solved by the new library: overestimation of criticality values for thermal fission reactors was improved by the modifications of fission cross sections and fission neutron spectra for 235 U; incorrect energy distributions of secondary neutrons from important heavy nuclides were replaced with statistical model calculations; the inconsistency between elemental and isotopic evaluations was removed for medium-heavy nuclides. Moreover, covariance data were provided for 20 nuclides. The reliability of JENDL-3.3 was investigated by the benchmark analyses on reactor and shielding performances. The results of the analyses indicate that JENDL-3.3 predicts various reactor and shielding characteristics better than JENDL-3.2.

π − , K + ) hyperon production inclusive spectra with pπ = 1.2 GeV/c measured at KEK on 12 C and 28 Si are analyzed by the semiclassical distorted wave model. Single-particle wave functions of the target nucleus are treated using Wigner transformation. This method is able to account for the energy and angular dependences of the elementary process in nuclear medium without introducing the factorization approximation frequently employed. Calculations of the (π + , K + ) Λ formation process, for which there is no free parameter since the Λ s.p. potential is known, demonstrate that the present model is useful to describe inclusive spectra. It is shown that in order to account for the experimental data of the Σ − formation spectra a repulsive Σ-nucleus potential is necessary whose magnitude is not so strong as around 100 MeV previously suggested.

The present status of the JENDL high-energy file is reported. The recent version (referred to as JENDL/HE-2007) contains neutron and proton cross section data for energies up to 3 GeV for 107 nuclides over the wide mass range from H to Am. The newly evaluated data for 41 nuclides have been added to the first version (JENDL/HE-2004) along with some revisions. The JENDL/HE-2007 includes neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double-differential cross sections of secondary light particles (n, p, d, t, 3 He, α, and π) and gamma-rays, isotope production cross sections, and fission cross sections in the ENDF-6 format. The evaluations were performed on the basis of experimental data, nuclear model calculations, and systematics based on measurements. The evaluated cross sections are compared with available experimental data and the other evaluations. Some results of benchmark tests with MCNPX codes are shown.