[en] The VIM Monte Carlo particle transport code uses detailed continuous-energy cross sections produced from ENDF/B data by a set of specialized codes developed or adapted for use at Argonne National Laboratory. ENDF/B-IV data were used until about 1979, and Version V data since then. These VIM libraries were extensively benchmarked against the MC²-2 code and against ZPR and ZPPR criticals for fast spectrum calculations, as well as other fast and thermal experiments and calculations. Recently, the cross section processing codes have been upgraded to accommodate ENDF/B-VI files, and a small library has been tested. Several fundamental tasks comprise the construction of a faithful representation of ENDF data for VIM calculations: (1) The resolved resonance parameters are converted to Doppler-broadened continuous-energy cross sections with energy grids suitable for linear-linear interpolation. (2) The unresolved resonance parameter distributions are sampled to produce many (40-400) resonance ladders in each energy band. These are converted to Doppler-broadened continuous energy resonance cross sections that are then binned by cross section, accumulating ladders until statistical convergence, the result being probability tables of total cross sections and conditional mean scattering and fission cross sections. VIM samples these tables at run time, and File 3 back ground cross sections are added. (3) Anisotropic angular distribution data are converted to angular probability tables. All other ENDF data are unmodified, except for format

[en] The CALOR code system, which is a complete radiation transport code system, is described with emphasis on the high-energy (> 20 MeV) nuclear collision models. Codes similar to CALOR are also briefly discussed. A current application using CALOR which deals with the development of the National Spallation Neutron Source is also given

[en] This report reviews the available information on W, the mean energy required to produce one ion pair in gases, liquids and solids, for a variety of radiations, and provides, when possible, suggested values for current usage. For gases, it provides a study of experimental methods, current theories and gas mixtures, leading to a compilation of experimental values with emphasis on energy dependence, and suggested values. For liquids and solids, references to more extensive discussions are given. 357 refs., 21 figs., 13 tabs

[en] One of the objectives of the AO 138-7 experiment on board the LDEF was a total dose measurement with Thermo Luminescent Detectors (TLD 100). Two identical cases, both including 5 TLDs inside various aluminum shields, are exposed to the space environment in order to obtain the absorbed dose profile induced. Radiation fluence received during the total mission length was computed, taking into account the trapped particles (solar maximum and solar minimum periods) and the cosmic rays; due to the magnetospheric shielding, the solar proton fluences are negligible on the LDEF orbit. The total dose induced by these radiations inside a semi-infinite plane shield of Al are computed with radiation transport codes. TLD reading are performed after flight; due to the mission duration increase, a post-flight calibration was necessary in order to cover the range of the flight induced dose. The results obtained, similar (+ or - 30 pct.) in both cases, are compared with the dose profile computation. In practice, these LDEF results, with less than a factor 1.4 between measurements and forecasts, reinforce the validity of the computation methods and models used for the long term evaluation of space radiation intensity on low inclination Earth orbits

[en] As advanced nodal methods become standard analysis tools for static, depletion, and transient applications, their adjoint calculations are also becoming more important. Adjoint solution methods corresponding to different nodal schemes have previously been reported. In Ref. 3, Lawrence showed the the adjoint solution for the interface-current nodal scheme used in the DIF3D nodal option can be obtained exactly for two-dimensional problems and to an excellent approximation for three-dimensional problems by using an intermediate solution (the so-called 'physical adjoint') and a similarity transformation. However, because the procedure used to obtain the similarity transformation was not described, its application to other interface-current nodal schemes has been limited. Here we discuss how to derive the similarity transformation between the matrices associated with the mathematical and physical adjoint equations and clarify why the previously developed transformation is only approximate in three dimensions

[en] This paper describes the parallelization of a radiation transport Monte Carlo simulation code that was used in the design of a particle detector

[en] A problem of determining the transport equation coefficient for energy and angular singularities of external radiation is discussed. The stationary transport equation is considered. The algorithms for the shown coefficient determination are proposed. 3 refs

[en] The monograph is a small manual to get a knowledge of ionizing and non-ionizing radiations. The main chapters are: - Electromagnetic radiations - Ionizing and non-ionizing radiations - Non-ionizing electromagnetic radiations - Ionizing electromagnetic radiation - Other ionizing radiations - Ionizing radiation effects - The Nuclear Safety Conseil

[en] Batan's standard code for calculation of integral kinetic parameters, Batan-ADJOINT-2D code, has been succesfully developed. The integral kinetic parameters considered are the effective delayed neutron fractions, neutron generation time and (prompt) neutron life time. The calculations demand both accurate regular (forward) and adjoint group neutron flux distributions. Batan-ADJOINT-2D code computes both the regular (forward) and the adjoint neutron flux distributions by solving numerically the forward and adjoint equations of multigroup neutron diffusion problem in two-dimensional, X-Y and R-Z reactor geometries with vacuum and/or reflective boundary condition. The spatial variables are treated with the finite difference method. The validity of the regular (forward) and adjoint neutron flux calculated with Batan ADJOINT-2D was verified using the 2DBUM, a generic neutron diffusion code. The verification results showed that the relative differences of the regular (forward) and adjoint group neutron flux distribution between the two codes were in the order of 10-3 % or less, while the relative differences for the eigenvalue were in the order of 10-5 %, for convergence criteria of 10-5. The relative differences of the calculated delayed neutron fractions calculated with the fluxes from the two codes were in the order of 10-4 % which proved the validity of Batan-ADJOINT-2D code. (author). 9 refs., 5 tabs., 3 figs

[en] A new version of the European Activation System (EASY), which includes the European Activation File (EAF) and the inventory codes FISPACT, has recently been developed. This version offers the possibility to calculate the effect of sequential charged particle reactions (SCPR), i.e., reactions of the charged particles produced by the primary neutron reactions. Such reactions were shown to be significant for pure materials. Some question remains as to their importance for realistic alloys with impurities. This paper describes the new features in EASY4 and reports results of calculations on a collection of fusion-relevant materials. Highlights from the conclusions are: (i) it is essential that correct impurity levels in materials be specified in order that activation properties can be determined; (ii) for realistic fusion-relevant materials studied here the effect of SCPR is unimportant compared with the estimated uncertainties in the dose rate; (iii) if special care were taken with impurity control in structural materials such as vanadium alloys and breeding materials such as FLiBe it would be necessary to include SCPR in inventory calculations for accurate predictions; in the case of iron-based alloys the contribution from SCPR is negligible even when no impurities are included. 9 refs, 4 figs, 2 tabs