RSICC CODE PACKAGE CCC-717
1. NAME AND TITLE
NMTC-JAM: High Energy Particle Transport Code System.
2. CONTRIBUTORS
Center for Neutron Science, Japan Atomic Energy Research Institute, Tokai-mura, Naka-run, Japan, through the Research Organization for Information Science and Technology (RIST).
3. CODING LANGUAGE AND COMPUTER
Fortran-77; Linux or Windows Pentium (C00717PC58600).
4. NATURE OF PROBLEM SOLVED
NMTC/JAM is an upgraded version of the code CCC-694/NMTC-JAERI97, which was developed in 1982 at JAERI and is based on the CCC-161/NMTC code system. NMTC/JAM simulates high energy nuclear reactions and nuclear meson transport processes. The applicable energy range of NMTC/JAM was extended in principle up to 200 GeV for nucleons and mesons by introducing the high energy nuclear reaction code Jet-Aa Microscopic (JAM) for the intra-nuclear cascade part. For the evaporation and fission process, a new model, GEM, can be used to describe the light nucleus production from the excited residual nucleus. According to the extension of the applicable energy, the nucleon-nucleus non-elastic, elastic and differential elastic cross section data were upgraded. In addition, the particle transport in a magnetic field was implemented for beam transport calculations. Some new tally functions were added, and the format of input and output of data is more user friendly. These new calculation functions and utilities provide a tool to carry out reliable neutronics study of a large scale target system with complex geometry more accurately and easily than with the previous model.
It implements an intranuclear cascade model taking account of the in-medium nuclear effects and the preequilibrium calculation model based on the exciton one. For treating the nucleon transport process, the nucleon-nucleus cross sections are revised to those derived by the systematics of Pearlstein. Moreover, the level density parameter derived by Ignatyuk is included as a new option for particle evaporation calculation. A geometry package based on the Combinatorial Geometry with multi-array system and the importance sampling technique is implemented in the code. Tally function is also employed for obtaining such physical quantities as neutron energy spectra, heat deposition and nuclide yield without editing a history file.
The code can simulate both the primary spallation reaction and the secondary particle transport in the intermediate energy region from 20 MeV to 3.5 GeV by the use of the Monte Carlo technique. The code has been employed in combination with the neutron-photon transport codes available to the energy region below 20 MeV for neutronics calculation of accelerator-based subcritical reactors, analyses of thick target spallation experimented and so on.
5. METHOD OF SOLUTION
High energy nuclear reactions induced by incident high energy protons, neutrons and pions are simulated with the Monte Carlo method by the intra-nuclear nucleon-nucleon reaction probabilities based on the BERTINI model followed by particle evaporation including high energy fission process. The JAM transport model is employed to simulate high energy nuclear reactions in the energy range of GeV. The ISOBAR code is employed as an alternative option for the intranuclear cascade calculation. The pre-equilibrium process is calculated by an exciton model in which proton, neutron, deuteron, triton, helium-3 and -particles are taken into account. Inter-nuclear transport processes of the incident and secondary nucleons in macroscopic material regions are simulated with the Monte Carlo method based on he O5R algorithm and a continuous slowing down model for charged particles. The nucleon-nucleus cross sections are revised to those derived by the systematics of Pearlstein.
6. RESTRICTIONS OR LIMITATIONS
Upper energy of an incident particle is limited to 200 GeV. When ISOBAR code is selected for intranuclear cascade calculation, the upper energy is limited to 1 GeV.
A geometry package based on the Combinatorial Geometry with multi-array system (MARS) is used for defining the geometry model of a problem. The importance sampling technique is implemented in the code to simulate the particle transport process effectively. Tally function is also employed for obtaining such physical quantities as neutron energy spectra, heat deposition and nuclide yield without editing a history file. The array size required for geometry model and tally is adjustable by changing the parameter size in an include file.
7. TYPICAL RUNNING TIME
The running time varies depending upon the target size and the incident beam energy.
8. COMPUTER HARDWARE REQUIREMENTS
The code runs on personal computers. Between 10 and 11Mb of memory are required. Several hundreds of mega-bytes to giga-bytes storage for cut-off neutron history storage. The memory and storage capacity is determined upon the parameter values and target size of problems.
9. COMPUTER SOFTWARE REQUIREMENTS
The developers ran NMTC-JAM on personal computers under Windows and SuSE Linux 7.2. The code was tested at RSICC on a Pentium IV running Windows XP with the author's included executable and on a PC Red Hat Linux 9.0 system with g77.
10. REFERENCES
a) included in package:
K. Niita, S. Meigo, H. Takada and Y. Ikeda, "High Energy Particle Transport Code NMTC/JAM," JAERI-Data/Code 2001-007 (March 2001).
b) background information:
H. Takade, N. Yoshizawa, N., K. Kosako, K. and Ishibashi, "An Upgrade Version of the Nuclear Meson Transport Code, NMTC/JAERI97," JAERI-Data/Code 98-005 (February 1998).
11. CONTENTS OF CODE PACKAGE
The package is transmitted on CD in a GNU compressed Unix tar file, which includes the referenced document in 10.a, source code, PC executable, data, and sample problem. Windows users may expand the package with WinZIP 8.0 or newer.
12. DATE OF ABSTRACT
December 2003.
KEYWORDS: NUCLEON; MESON; MONTE CARLO; COMPLEX GEOMETRY; PROTON; NEUTRON; SPALLATION