[en] This report contains the bibliographic index data on photonuclear reactions and on their inverse ones, in the format similar to CINDA for neutron nuclear data. As photonuclear reactions the electron-induced reaction data are also included. As the inverse reactions considered are those induced by neutron, proton, deuteron, triton, helion and alpha particles. The index covers major journals on nuclear data published in 1995 to 1992, for all nuclides through hydrogen (H) to einsteinium (Es). The bibliographic index contains information on target nucleus, incident beam, type of reaction and quantity, energy range of incident beam, laboratory, type of work, reference citations, first author's name, and short comment. The index also contains the indication for information on cross-section data. All the index data are listed in the order of target element, target, mass and incident particle, and in the chronological order of reference data. Also a brief description is given on the data format, the abbreviations used and the journals surveyed. (author)

[en] This issue is the collection of the papers presented at the title meeting. The 35 of the presented papers are indexed individually. (J.P.N.)

[en] Description of problem or function: RESENDD reconstructs resonance cross sections from evaluated resonance parameters in the ENDF/B format. If needed, Doppler broadened cross sections are also calculated. Both ENDF/B-IV and ENDF/B-V format are available for input and output files. Formulas used in RESENDD for reconstruction of resonance cross sections are given in BNL-NCS-50496(ENDF 102) 'Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF'. As an exception, the multilevel Breit-Wigner formula used in RESENDD is different from BNL-NCS-50496. The calculation method for Doppler effect is the same as that of SIGMA1 (UCRL-50400 Vol. 17, Part b, Rev. 2, by D.E. Cullen)

[en] The nuclear charge distribution function is derived from statistical theory as a function of the most probable charge transfer variable defined by the most stable charges of fission fragments. The fine structures observed in the charge distribution width, skewness and excess can be described by the present formula in terms of charge shift due to pairing effects, as well as in asymmetric terms of nuclear mass. According to an investigation on the fine structure by a semi-empirical method, some remarks are given for the saddle and scission states. (author)

[en] The present status of experimental and evaluated resonance parameters of ²³⁸U are briefly reviewed. The parameters stored in JENDL-2 are accurate enough for low lying levels. At high energies, activities of NEANDC Task force on ²³⁸U discrepancies are summarized. For JENDL-3, the resonance parameters will be evaluated up to 10 keV, if possible, by taking into account new values of parameters obtained by Olsen. Tentative calculation from the Olsen's parameters is shown. (author)

[en] The simultaneous evaluation for the fission cross section of ²³⁵U, ²³⁸U, ²³⁹Pu, ²⁴⁰Pu and ²⁴¹Pu, and the capture cross sections of ¹⁹⁷Au and ²³⁸U was performed by the JNDC Subworking Group on Heavy Nuclide Data. The evaluated data was obtained in the energy range from 50 keV to 20 MeV by means of the generalized least-squares method and the B-spline functions. The presently obtained fission cross sections of ²³⁵U and ²³⁹Pu are a few percent smaller than the JENDL-2 data in the energy range below 1 MeV. (author)

[en] The ENDF/B format is adopted for JENDL. In this paper, the basic things of the ENDF/B format are explained and differences among recent versions of the ENDF/B format are summarized. (author)

[en] RESENDD is a computer program to calculate resonance cross sections from evaluated resonance parameters in the ENDF/B format. This program was improved from RESEND by modifying the multi-level Breit-Wigner formula, adding a function of Doppler broadening, and so on. This report explains functions of RESENDD and describes input data. Some examples are also given. (author)

[en] Neutron nuclear data of ²⁵²Cf and ²⁵⁰Bk have been evaluated in the neutron energy range from 10^-5 eV to 20 MeV. The cross sections evaluated are the total, elastic and inelastic scattering, (n, 2n), (n, 3n), (n, 4n) reaction, fission and capture cross sections. For the both nuclides, cross sections below 30 keV were represented with resolved and unresolved resonance parameters. For ²⁵²Cf, the resolved resonance parameters were evaluated in the energy range from 10^-5 eV to 1 keV and the unresolved resonance parameters above 1 keV. For ²⁵⁰Bk, no resonance parameters have been reported. Therefore, hypothetical resolved resonance parameters were given below 100 eV. In addition, angular and energy distributions of emitted neutrons and average number of emitted neutrons per fission were also evaluated. Existing experimental data are only those for the fission cross section of ²⁵²Cf, thermal cross sections and resonance integrals of ²⁵²Cf and the fission cross section of ²⁵⁰Bk at the thermal neutron energy. The present evaluation, therefore, was mainly based on the systematics of the data from neighboring nuclides and optical- and statistical-model calculations. (author)

[en] The evaluation and compilation work for JENDL-2 was started in 1977. The purpose of JENDL-2 is to modify the defects of JENDL-1 and to extend the application fields of JENDL to thermal reactor, fusion and shielding fields as well as fast reactor calculation. The number of nuclides of which data are stored in JENDL-2 will be increased to a hundred and a few tens. The data of important nuclides such as structural materials and heavy nuclides have been compiled already. The compilation of all the data will have been completed in 1981. In this report, the present status of JENDL-2 is discussed, especially the data of important nuclides. (author)