RSICC CODE PACKAGE CCC-747
1. NAME AND TITLE
TRIPOLI-4.4: Code System for Coupled Neutron, Photon, Electron, Positron, 3-D, Time Dependent, Monte-Carlo, Transport.
RESTRICTIONS:
RSICC is authorized to distribute TRIPOLI 4.4 for research and education purposes only. Non-commercial requesters from NEA Data Bank member countries are advised to order TRIPOLI from the NEA Data Bank. Non-commercial users from other OECD member countries (specifically Australia, Canada, and the United States) may order TRIPOLI from RSICC. Users from non-OECD member countries and all commercial requesters are advised to contact the NEA Data Bank. They will transmit the requests to CEA, who will deal directly with these requests.
DATA LIBRARIES
GALILEE 0.2 processed libraries in a TRIPOLI-4 specific format based on JEFF31, FENDL21, JENDL33, ENDFB7R0, and EPDL97. Also included are libraries produced using NJOY in a TRIPOLI-4 specific format based on JEF2, ENDFB6R4, and ENDL.
2. CONTRIBUTORS
Commissariat à l'énergie atomique, CEA/SACLAY, Cedex, France, through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France.
3. CODING LANGUAGE AND COMPUTER
Fortran 77 and C; SUN, IBM, Digital, Compaq and Linux based PCs
(RSICC ID: C00747MNYWS00). (NEADB identifier is NEA-1716/06.)
4. NATURE OF PROBLEM SOLVED
TRIPOLI-4 is a general purpose radiation transport code. It uses the Monte Carlo method to simulate neutron and photon behavior in three-dimensional geometries. The main areas of applications include but are not restricted to: radiation protection and shielding, nuclear critic ality safety, fission and fusion reactor design, nuclear instrumentation. In addition, it can simulate electron-photon cascade showers.
It computes particle fluxes and currents and several related physical quantities such as, reaction rates, dose rates, heating, energy deposition, effective multiplication factor, perturbation effects due to density, concentration or partial cross-section variations.
Neutron cross-sections are available for the following nuclear evaluations: JEFF-3.1, ENDF/B-VII.0, JENDL-3.3, FENDL-2.1. NJOY-99.259 and CALENDF-2005 were used in GALILEE 2, which was used to process the libraries. Cross-sections and probability tables are given at 294 K. The bound nuclei cross-sections are given at every temperature available from the evaluation. Gamma cross-sections are all given from the EPDL-97 evaluation. Additional data libraries distributed with the TRIPOLI-4 include:
- ENDFB6R4: neutron, gamma data library
- ENDL: gamma data library
- JEF2: neutron, gamma data library
- Mott-Rutherford: electron, positron cross-section library
- Qfission: energy release during fission library
Types of particles Neutron, gamma, electron, positron.
Nuclear data ENDF-6 format. Cross sections processed
by NJOY code system. Pointwise cross
section representation. Probability
tables (PT) representation possible in
unresolved energy range (PT produced by
CALENDF code).
Energy ranges For neutrons and gamma the energy range
is the same as range specified into the
evaluation in ENDF-6 format.
Neutrons : 0. - 150 MeV
Gamma : 0 - 100 MeV
For Electrons/positrons :
1 MeV - several GeV (with bremsstrahlung
gamma rays).
Geometry 3-D surface and combinatorial, network
and network of networks.
Sources General factorised description: space,
energy, angle, time
Calculated physical See table below.
quantities, estimators
Biasing Exponential Transform,
splitting/roulette. Automatisation of
biasing.
Time dependent transport for neutrons.
Perturbation Density, concentration of isotopes, partial cross-sections.
Coupled particle (neutron, gamma), (electron, positron, gamma)
transport
Qualification Shielding (SINBAD benchmarks),
criticality (ICSBEP benchmarks)
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Estimated physical quantities Type of estimator
volume surface point
Total flux Track length yes yes
and collision
Integrated flux Track length yes yes
per energy group and collision
and time interval
Integrated flux Track length yes yes
per energy group and and collision
angular mesh
Integrated flux per Track length yes yes
energy group and collision
Total current yes
Integrated current yes
per energy group and
time interval
Integrated current yes
per energy group and
angular mesh
Integrated flux per yes
energy group
Reaction rate on Track length yes
whole energy range and collision
Reaction rate per Track length yes
energy group and collision
time interval
Reaction rate per Track length yes
energy group collision
Deposited energy collision
Equivalent dose rate Track length yes yes
collision
Gamma production yes
Multiplication factor yes (kstep, kcoll, ktrack, kij)
Eigen value of a yes
criticality
configuration
Cross section yes
(partial or total)
perturbations
Density or yes
concentration
perturbation
New features available in TRIPOLI-4 version 4:
1. New biasing features: It is possible to store and re-use importance maps. Biasing
with a plane or spherical surface has been added (cylindrical was already
available).
2. Neutron collision in multigroup homogenized mode: anisotropy up to the order
3 in the Legendre polynomial expansion (P3).
3. Display of the collision sites.
4. ENDF format evaluations: Mixed representation of the anisotropy from file 4:
Legendre format used at low energy and tabulated probability distributions at
high energy (eg O16 from ENDFB6R8). cf ENDF-102 Data formats and procedures for
the evaluated nuclear data file ENDF-6. 07/1990, revised 04/2001, pages 4.3 to
4.5.
5. Computation of the gamma source produced by neutrons.
6. Output format for all results: the -a execution option allows even zero
results to be displayed in the output. Although the standard deviation is
infinite in this case, for reason of compatibility with the rest of the code
the output file gives also a zero value for the standard deviation.
7. Verbose level for output warnings: the code now gives only the most
important information to the user. The -v option allows the warnings, the -D
option gives the same verbose level as previous versions.
8. Photons reactions rates: In the RESPONSES command, interaction code 100
(coherent scattering), 101 (incoherent scattering), 102 (photoelectric effect),
103 (pair production) and 106 (total photon) are now available.
9. XML format output : In the SIMULATION command, the "XML_EXPORT"
keyword allows the user to get an XML format output file. Any post-processing
tool that can cope with XML format may be used to process this file.
10. ENDF format evaluations:
- By default use of evaluations produced by Njoy99. (version 81).
- It is possible to use jeff3.1, endfb7 and jendl3.3 evaluations:
- the maximum order of Legendre polynomials is no longer limited to 21.
- ENDF format 2D interpolation "unit-base" (file 6) is now supported.
11. Combinatorial geometry checks: It is now possible to choose the number of
points for the non-overlapping tests of combinatorial volumes. The keyword is
"TEST_GENERATED_POINTS n" (200 by default).
The keyword may be written:
- only once, at the beginning (after the TITLE keyword)
- or as many times as necessary in the GEOMETRY command, just before a VOLU
keyword (for each combinatorial volume, the number of generated points refers
to the last TEST_GENERATED_POINTS keyword).
12. Green's functions files.
13. Neutronics-shielding coupling.
14. Responses, scores, biasing names: It is possible to give names (instead of
giving a number) to responses and scores. It is necessary to give names to
responses, scores and biasings for neutronics-shielding coupled simulations.
15. Units: The -u execution option allows the code to output scores with their
units.
5. METHOD OF SOLUTION
The geometry package allows the user to describe a three dimensional configuration by means of surfaces (as in the MCNP code) and also through predefined shapes combine with operators (union, intersection, subtraction...). It is also possible to repeat a pattern to build a network of networks.
TRIPOLI-4 can use four different types of cross-sections representation:
Neutron and photon transport is governed by the Boltzmann equation. The code resolves this equation by the Monte Carlo method. This requires a random generator: TRIPOLI4 uses drand48 in non-parallel calculations and gfsr for parallel calculations. The calculation is carried out by division into several batches of particles, each batch containing an equal number of source particles. Within a batch, the code monitors particles in the following manner:
1) The source particles are first generated by random selection according to the distribution supplied by the user (in space, energy, angle and time).
2) Each particle is monitored individually:
a. Between two impacts the trajectory is a straight line (since they are neutral particles). The distance between two impacts depends on the total cross-section of the medium.
b. When an impact occurs, sampling concerns the impacted isotope (as a function of the concentration), then the type of interaction (as a function of the isotope) and finally the energy and direction after impact (as a function of the interaction and initial energy).
The mean results for each quantity required (based on the number of source particles per batch) are calculated over all the batches, each of which can be considered to be a sample. The final scores are obtained by calculating the average for the number of batches making up the total results. Standard deviation can then be calculated for the final values. If the number of batches is low and the central limit theorem does not apply, the code can use suitable bootstrap techniques.
If there is high attenuation, biasing techniques must be used to avoid excessive calculation times. In this case, the code performs an exponential transformation. (An importance factor is assigned to each point of phase space so that biased cross-sections can be used).
Several biasing techniques are implemented in TRIPOLI-4: exponential biasing scheme, quota sampling and collision biasing. The biasing is automatised from a Dijkstra algorithm.
The communication library has been written to achieve message passing between the different processes involved in the simulation. This library only cares of data that are exchange between processes while the parallelism library deals with actions that must be achieved by the processes.
6. RESTRICTIONS OR LIMITATIONS
See distribution restrictions noted above.
7. TYPICAL RUNNING TIME
Run times vary depending largely on the number of simulated particle histories. Test cases completed in approximately 12 minutes. Currently, 10s up to 100s of millions of particle histories are simulated
8. COMPUTER HARDWARE REQUIREMENTS
TRIPOLI-4 runs on Unix workstations (SUN, IBM, Digital) and on Linux based PCs. TRIPOLI-4.4 requires 1.5Gbytes of disk space. The associated Galilee libraries require ~14 Gbytes of disk space.
9. COMPUTER SOFTWARE REQUIREMENTS
TRIPOLI 4.4 runs under Linux or Unix workstations; this release does not run under Windows. At RSICC, TRIPOLI was tested by running the developers’ executables on an AMD Opteron under Red Hat Enterprise Linux WS release 4 version 2.6.9 and on a PC running Ubuntu-8.04 (Hardy Heron) 2.6.24 kernel. At NEADB, TRIPOLI was tested on a Pentium III under Red Hat Linux 8.2.2-5.
No source files are included. Developers compiled and tested on the following architectures.
· Solaris-sparc (5.7, 5.8 and 5.9)
· linux-intel (2.4.xx, 2.6.xx)
· osf1 (V5.1)
· aix (5.1 and 5.3)
Executables created by the author for each of these systems are included in the package, as well as installation scripts and test cases to verify the correct installation of the executables.
Depending on the operating system, the exact version of the system libraries used in Tripoli4 can be available or not. In case, there are some missing libraries, the system manager might be able to install them. The ldd command used on the binary (in CODE/bin/<os>/static-tripoli4-4.4) can help to identify if there are missing libraries. The environment variable LD_LIBRARY_PATH can also be used to specify directories containing the otherwise missing libraries.
10. REFERENCES
10.a included in package in electronic files:
10,b
References concerning theory and functionalities – not
included in pkg:
- J. P. Both, A. Mazzolo, O. Petit, Y. Peneliau, B. Roesslinger:
User Manual for version 4.3 of the TRIPOLI-4 Monte Carlo method particle
transport computer code, CEA-Report : CEA-R-6044, DTI, CEA/Saclay, France, 2003
- J.P. Both, H. Derriennic, B. Morillon, J.C. Nimal:
"A Survey of TRIPOLI-4", Proceedings of the 8th International
Conference on Radiation Shielding, Arlington, Texas, USA, 24-28 avril 1994, pp.
373-380.
- B. Morillon:
"Methode de Monte Carlo non analogue - Application a la simulation des
neutrons", Note CEA-N-2805, CEA/Saclay, janvier 1996.
- J.P. Both, Y.K. Lee:
"Computations of Homogenised Multigroup Cross Sections with the Monte
Carlo Code TRIPOLI 4", Proceedings SARATOGA 1997, JIC MM &SNA,
Saratoga Springs, New York, USA, october, 1997, p. 439.
- Y. Peneliau, J.P. Both:
"Parallelization of the Monte Carlo Code TRIPOLI-4", Mathematical and
Computation, Reactor Physics and Environmental Analysis in Nuclear
Applications, Madrid, Spain, Sept. 1999, p. 412.
- J. P. Both:
Treatment of Cross Section Uncertainties in the Transport Monte Carlo Code TRIPOLI-4,
ICRS'9, Tsukuba, Ibaraki, Japan, october 17-22, 1999, Journal of Nuclear
Science and Technology, Supplement 1, pp. 420-42, March 2000, pp. 420-426.
- Y. Peneliau:
"Electron Photon Shower Simulation TRIPOLI-4 in Monte Carlo Code",
Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and
Applications, Lisbon, Portugal, Oct. 2000.
- J. P. Both, Y.K. Lee, A. Mazzolo, O. Petit, Y. Peneliau, B. Roesslinger, M.
Soldevila:
TRIPOLI-4 - A Three Dimensional Polykinetic Particle Transport Monte Carlo
Code, SNA'2003, Paris Sept. 2003.
10.c references concerning qualification - not included in pkg:
- Y.K. Lee, G. Neron, J.P. Both, Y. Peneliau, C. Diop:
"Validation of Monte Carlo Code TRIPOLI-4 with PWR Critical Lattices by
using JEF 2.2 and ENDF/B-VI Evaluations". JIC MM &SNA, Saratoga
Springs, New York, USA, October, 1997, p. 253.
- Y.K. Lee, S.H. Zheng, G. Neron, J.P. Both, Y. Peneliau, C. Diop:
"ICNC'9, Cristal, Criticality Safety Package Validation : Tripoli-4 Monte
Carlo Code, JEF2.2 Library and ICSBEP Experiments", Sixth International
Conference on Nuclear Criticality Safety. Versailles, France, 20-24 September
1999.,
- Y. K. Lee:
"Analysis of the NRC PCA Pressure Vessel Dosimetry Benchmark Using
TRIPOLI-4.3 Monte Carlo Code and ENDF/B-VI, JEF-2.2 and IRDF-90 Libraries,
Nuclear Mathematical and Computational Science", Gatlinburg, Tennessee,
USA, April 6-11 2003.
- E. Gagnier, Y. K. Lee, L. Aguiar, N. Vedrenne:
Validation of the 3D Transport Monte Carlo Code TRIPOLI-4.3 for moderated and unmoderated
metallic fissile media configurations with Jef-2.2 and ENDF/B6.r4 cross section
evaluations ; Y. K. Lee, Analysis of the LEU-COMP-THERM-049 Maracas Critical
Configurations Using TRIPOLI-4.3 3D Lattices Geometry and JEFF-3.0 Library,
ICNC'2003, Tokai-Mura, October 2003.
- Y. K. Lee, Analysis of the LEU-COMP-THERM-049 Maracas Critical Configurations
Using TRIPOLI-4.3 3D Lattices Geometry and JEFF-3.0 Library.
11. CONTENTS OF CODE PACKAGE
The package is transmitted on two DVD discs which contain the reports listed in section 10.a above, scripts, executable files, data files and test cases.
12. DATE OF ABSTRACT
April 2009.
KEYWORDS:
COMPLEX GEOMETRY; COUPLED NEUTRON-GAMMA-RAY; ELECTRON CROSS SECTIONS; CRITICALITY CALCULATIONS; MONTE CARLO; NEUTRON; POSITRON; TIME-DEPENDENT