NEA-1673 MVP/GMVP II.
MVP/GMVP II, MC Codes for Neutron & Photon Transport Calc. based on Continuous Energy and Multigroup Methods
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, RESTRICTIONS, TYPICAL RUNNING TIME, FEATURES, RELATED OR AUXILIARY PROGRAMS, STATUS, REFERENCES, HARDWARE REQUIREMENTS, LANGUAGE, SOFTWARE REQUIREMENTS, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| MVP/GMVP II | NEA-1673/01 | Arrived | 16-DEC-2005 |
| MVP/GMVP II | NEA-1673/02 | Arrived | 16-DEC-2005 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1673/01 | PC Windows | |
| NEA-1673/02 | Linux-based PC,UNIX W.S. |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
(1) Problems to be solved:
MVP/GMVP can solve eigenvalue and fixed-source problems. The multigroup code GMVP can solve forward and adjoint problems for neutron, photon and neutron-photon coupled transport. The continuous-energy code MVP can solve only the forward problems. Both codes can also perform time-dependent calculations.
(2) Geometry description:
MVP/GMVP employs combinatorial geometry to describe the calculation geometry. It describes spatial regions by the combination of the 3-dimensional objects (BODIes). Currently, the following objects (BODIes) can be used.
- BODIes with linear surfaces : half space, parallelepiped, right parallelepiped, wedge, right hexagonal prism
- BODIes with quadratic surface and linear surfaces : cylinder, sphere, truncated right cone, truncated elliptic cone, ellipsoid by rotation, general ellipsoid
- Arbitrary quadratic surface and torus
The rectangular and hexagonal lattice geometry can be used to describe the repeated geometry. Furthermore, the statistical geometry model is available to treat coated fuel particles or pebbles for high temperature reactors.
(3) Particle sources:
The various forms of energy-, angle-, space- and time-dependent distribution functions can be specified.
(4) Cross sections:
The ANISN-type PL cross sections or the double-differential cross sections can be used in the multigroup code GMVP. On the other hand, the specific cross section libraries are used in the continuous-energy code MVP. The libraries are generated from the evaluated nuclear data (JENDL-3.3, ENDF/B-VI, JEF-3.0 etc.) by using the LICEM code. The neutron cross sections in the unresolved resonance region are described by the probability table method. The neutron cross sections at arbitrary temperatures are available for MVP by just specifying the temperatures in the input data.
(5) Boundary conditions:
Vacuum, perfect reflective, isotropic reflective (white), periodic boundary conditions can be specified.
(6) Variance reduction techniques:
The basic variance reduction techniques Russian roulette kill and splitting are implemented. In addition, importance and weight window based on them are available. Path stretching and source biasing can be also used.
(7) Estimator:
The track length, collision, point and surface crossing estimators are available. The eigenvalue is estimated by the track length, collision and analog estimators for neutron production and neutron balance methods. In the final estimation, the most probable value and its variance are calculated by the maximum likelihood method with the combination of the estimators.
(8) Tallies:
GMVP calculates the eigenvalue, the particle flux and reaction rates in each spatial region, each energy group and each time bin for each material, each nuclide and each type of reactions, and their variances as the basic statistical parameters. In addition to these physical quantities, MVP calculates the effective microscopic and macroscopic cross sections and the corresponding reaction rates in the specified regions. These quantities are basically tallied for each spatial region but can be tallied for the arbitrary combination of the regions with options. Furthermore, the calculated quantities are output to files and can be then used for the input data of a drawing program mentioned later or a burnup calculation code MVP-BURN.
(9) Drawing geometry:
The CGVIEW code draws the cross-sectional view on an arbitrary plane and output it on a display or in the postscript or encapsulated postscript form. These functions are useful for checking the calculation geometry.
(10) Burnup calculation:
The auxiliary code MVP-BURN implemented in the MVP/GMVP system is available for burnup calculations.
(11) Parallelism:
Parallel calculations can be performed with standard libraries MPI and PVM.
(12) Other capabilities:
MVP/GMVP has a capability of reactor noise analysis based on simulation of Feynman-alpha experiments.
(1) Problems to be solved:
MVP/GMVP can solve eigenvalue and fixed-source problems. The multigroup code GMVP can solve forward and adjoint problems for neutron, photon and neutron-photon coupled transport. The continuous-energy code MVP can solve only the forward problems. Both codes can also perform time-dependent calculations.
(2) Geometry description:
MVP/GMVP employs combinatorial geometry to describe the calculation geometry. It describes spatial regions by the combination of the 3-dimensional objects (BODIes). Currently, the following objects (BODIes) can be used.
- BODIes with linear surfaces : half space, parallelepiped, right parallelepiped, wedge, right hexagonal prism
- BODIes with quadratic surface and linear surfaces : cylinder, sphere, truncated right cone, truncated elliptic cone, ellipsoid by rotation, general ellipsoid
- Arbitrary quadratic surface and torus
The rectangular and hexagonal lattice geometry can be used to describe the repeated geometry. Furthermore, the statistical geometry model is available to treat coated fuel particles or pebbles for high temperature reactors.
(3) Particle sources:
The various forms of energy-, angle-, space- and time-dependent distribution functions can be specified.
(4) Cross sections:
The ANISN-type PL cross sections or the double-differential cross sections can be used in the multigroup code GMVP. On the other hand, the specific cross section libraries are used in the continuous-energy code MVP. The libraries are generated from the evaluated nuclear data (JENDL-3.3, ENDF/B-VI, JEF-3.0 etc.) by using the LICEM code. The neutron cross sections in the unresolved resonance region are described by the probability table method. The neutron cross sections at arbitrary temperatures are available for MVP by just specifying the temperatures in the input data.
(5) Boundary conditions:
Vacuum, perfect reflective, isotropic reflective (white), periodic boundary conditions can be specified.
(6) Variance reduction techniques:
The basic variance reduction techniques Russian roulette kill and splitting are implemented. In addition, importance and weight window based on them are available. Path stretching and source biasing can be also used.
(7) Estimator:
The track length, collision, point and surface crossing estimators are available. The eigenvalue is estimated by the track length, collision and analog estimators for neutron production and neutron balance methods. In the final estimation, the most probable value and its variance are calculated by the maximum likelihood method with the combination of the estimators.
(8) Tallies:
GMVP calculates the eigenvalue, the particle flux and reaction rates in each spatial region, each energy group and each time bin for each material, each nuclide and each type of reactions, and their variances as the basic statistical parameters. In addition to these physical quantities, MVP calculates the effective microscopic and macroscopic cross sections and the corresponding reaction rates in the specified regions. These quantities are basically tallied for each spatial region but can be tallied for the arbitrary combination of the regions with options. Furthermore, the calculated quantities are output to files and can be then used for the input data of a drawing program mentioned later or a burnup calculation code MVP-BURN.
(9) Drawing geometry:
The CGVIEW code draws the cross-sectional view on an arbitrary plane and output it on a display or in the postscript or encapsulated postscript form. These functions are useful for checking the calculation geometry.
(10) Burnup calculation:
The auxiliary code MVP-BURN implemented in the MVP/GMVP system is available for burnup calculations.
(11) Parallelism:
Parallel calculations can be performed with standard libraries MPI and PVM.
(12) Other capabilities:
MVP/GMVP has a capability of reactor noise analysis based on simulation of Feynman-alpha experiments.
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4. METHODS
MVP and GMVP are based on the continuous-energy and multigroup method, respectively. In the continuous-energy method, all reactions are treated explicitly as given in evaluated nuclear data. Pointwise cross sections and angular/energy distributions are basically used for particle tracking. For neutron thermal scattering, the free gas model is used to take into account the thermal motion of target nuclei or the scattering law data S(alpha,beta) and elastic thermal scattering representation in the ENDF format are used to take into account the binding effect in liquids and solids. In the unresolved resonance region of neutron cross sections, the probability table method is used. For photon reactions, detailed and simple models are available. The detailed model includes the generation of fluorescent X-rays in the photoelectric effect and the correction factor of the Klein-Nishina differential cross section for the incoherent scattering but the simple model does not include them. In both models, Bremsstrahlung photons can be optionally taken into account in the thick target approximation. Energy ranges are from 0.00005 eV to 20 MeV for neutrons and from 1 keV to 100 MeV for photons. In the multigroup method, all reactions are treated according to multigroup cross section data given by users.
MVP and GMVP are based on the continuous-energy and multigroup method, respectively. In the continuous-energy method, all reactions are treated explicitly as given in evaluated nuclear data. Pointwise cross sections and angular/energy distributions are basically used for particle tracking. For neutron thermal scattering, the free gas model is used to take into account the thermal motion of target nuclei or the scattering law data S(alpha,beta) and elastic thermal scattering representation in the ENDF format are used to take into account the binding effect in liquids and solids. In the unresolved resonance region of neutron cross sections, the probability table method is used. For photon reactions, detailed and simple models are available. The detailed model includes the generation of fluorescent X-rays in the photoelectric effect and the correction factor of the Klein-Nishina differential cross section for the incoherent scattering but the simple model does not include them. In both models, Bremsstrahlung photons can be optionally taken into account in the thick target approximation. Energy ranges are from 0.00005 eV to 20 MeV for neutrons and from 1 keV to 100 MeV for photons. In the multigroup method, all reactions are treated according to multigroup cross section data given by users.
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6. TYPICAL RUNNING TIME
The following is the CPU time for sample problems.
MVP
Linux* PC Windows**
sample1 : 12 min 8 sec, 3 hours 37 min 4 sec
sample1t : 1 min 39 sec, 21 min 26 sec
sample2 : 2 min 39 sec, 38 min 50 sec
sample2t : 40 sec, 8 min 34 sec
sample3 : 9 min 59 sec, 2 hours 22 min 19 sec
sample3t : 12 sec, 4 min 3 sec
sample4 : 3 min 44 sec, 1 hours 0 min 30 sec
sample5 : 1 min 23 sec, 11 min 56 sec
sample6 : 23 sec, 6 min 21 sec
sample7 : 1 min 8 sec, 16 min 28 sec
sample8 : 27 sec, 7 min 40 sec
sample9 : 20 sec, 7 min 54 sec
GMVP
Linux* PC Windows**
sample1 : 16 sec, 3 min 29 sec
sample2 : 3 sec, 1 min 6 sec
sample3 : 39 sec, 6 min 39 sec
sample4 : 49 sec, 12 min 47 sec
sample5 : 1 min 16 sec, 18 min 48 sec
sample6 : 9 sec, 2 min 34 sec
sample7 : 17 sec, 3 min 14 sec
sample8 : 22 sec, 4 min 39 sec
* Linux, Intel Itanium2 1.6GHz, Single task calculation.
** Windows XP, Intel Xeon 2.8GHz , Single task calculation.
The following is the CPU time for sample problems.
MVP
Linux* PC Windows**
sample1 : 12 min 8 sec, 3 hours 37 min 4 sec
sample1t : 1 min 39 sec, 21 min 26 sec
sample2 : 2 min 39 sec, 38 min 50 sec
sample2t : 40 sec, 8 min 34 sec
sample3 : 9 min 59 sec, 2 hours 22 min 19 sec
sample3t : 12 sec, 4 min 3 sec
sample4 : 3 min 44 sec, 1 hours 0 min 30 sec
sample5 : 1 min 23 sec, 11 min 56 sec
sample6 : 23 sec, 6 min 21 sec
sample7 : 1 min 8 sec, 16 min 28 sec
sample8 : 27 sec, 7 min 40 sec
sample9 : 20 sec, 7 min 54 sec
GMVP
Linux* PC Windows**
sample1 : 16 sec, 3 min 29 sec
sample2 : 3 sec, 1 min 6 sec
sample3 : 39 sec, 6 min 39 sec
sample4 : 49 sec, 12 min 47 sec
sample5 : 1 min 16 sec, 18 min 48 sec
sample6 : 9 sec, 2 min 34 sec
sample7 : 17 sec, 3 min 14 sec
sample8 : 22 sec, 4 min 39 sec
* Linux, Intel Itanium2 1.6GHz, Single task calculation.
** Windows XP, Intel Xeon 2.8GHz , Single task calculation.
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8. RELATED OR AUXILIARY PROGRAMS
CGVIEW : Program to draw cross-sectional views of MVP/GMVP calculation geometry.
MVPART : Program to generate cross section data at arbitrary temperatures.
MVPBURN : Program to perform burnup calculations with MVP.
NTXT2LB : Program to convert the text form of MVP libraries into the binary form.
NLB2TXT : Program to convert the binary form of MVP libraries into the text form.
GMVPLBCV : Program to convert the text form of multigroup cross section data into the binary form.
MVPFAT : Preprocessor for FORTRAN source codes.
The following MVP libraries are included in this package.
Neutron libraries (text form) : JENDL-3.3, JENDL-3.2, ENDF/B-VI.8, JEF-3.0, JEF-2.2
Photon library (text form)
Electron library (text form)
Dosimetry library (text form)
CGVIEW : Program to draw cross-sectional views of MVP/GMVP calculation geometry.
MVPART : Program to generate cross section data at arbitrary temperatures.
MVPBURN : Program to perform burnup calculations with MVP.
NTXT2LB : Program to convert the text form of MVP libraries into the binary form.
NLB2TXT : Program to convert the binary form of MVP libraries into the text form.
GMVPLBCV : Program to convert the text form of multigroup cross section data into the binary form.
MVPFAT : Preprocessor for FORTRAN source codes.
The following MVP libraries are included in this package.
Neutron libraries (text form) : JENDL-3.3, JENDL-3.2, ENDF/B-VI.8, JEF-3.0, JEF-2.2
Photon library (text form)
Electron library (text form)
Dosimetry library (text form)
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| Package ID | Status date | Status |
|---|---|---|
| NEA-1673/01 | 16-DEC-2005 | Masterfiled Arrived |
| NEA-1673/02 | 16-DEC-2005 | Masterfiled Arrived |
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10. REFERENCES
- T. Mori, K. Okumura and Y. Nagaya:
Development of the MVP Monte Carlo Code at JAERI, Trans. Am. Nucl. Soc., 84, 45 (2001).
- T. Mori, K. Okumura and Y. Nagaya:
Status of JAERI's Monte Carlo Code MVP for Neutron and Photon Transport Problems, Monte Carlo 2000 Conference, Lisbon, 23-26 October 2000, Proceeding p.625 (2000).
- T. Mori and M. Nakagawa:
MVP/GMVP : General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods, JAERI-Data/Code 94-007 (1994) [in Japanese].
- T. Mori, M. Nakagawa and M. Sasaki:
Vectorization of Continuous Energy Monte Carlo Method for Neutron Transport Calculation, J. Nucl. Sci. Technol., Vol. 29, No. 4, pp. 325-336 (1992).
- M. Nakagawa, T. Mori and M. Sasaki:
Monte Carlo Calculations on Vector Supercomputers using GMVP, Prog. Nucl. Energy, 24, 183 (1990).
- T. Mori, K. Okumura and Y. Nagaya:
Development of the MVP Monte Carlo Code at JAERI, Trans. Am. Nucl. Soc., 84, 45 (2001).
- T. Mori, K. Okumura and Y. Nagaya:
Status of JAERI's Monte Carlo Code MVP for Neutron and Photon Transport Problems, Monte Carlo 2000 Conference, Lisbon, 23-26 October 2000, Proceeding p.625 (2000).
- T. Mori and M. Nakagawa:
MVP/GMVP : General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations based on Continuous Energy and Multigroup Methods, JAERI-Data/Code 94-007 (1994) [in Japanese].
- T. Mori, M. Nakagawa and M. Sasaki:
Vectorization of Continuous Energy Monte Carlo Method for Neutron Transport Calculation, J. Nucl. Sci. Technol., Vol. 29, No. 4, pp. 325-336 (1992).
- M. Nakagawa, T. Mori and M. Sasaki:
Monte Carlo Calculations on Vector Supercomputers using GMVP, Prog. Nucl. Energy, 24, 183 (1990).
NEA-1673/01, included references:
- Y. Nagaya, K. Okumura, T. Mori and M. Nakagawa:MVP/GMVP II : General Purpose Monte Carlo Codes for Neutron and Photon
Transport Calculations based on Continuous Energy and Multigroup Methods
JAERI-1348 (2005)
- K. Okumura, Y. Nagaya and T. Mori:
MVP-BURN: Burn-up Calculation Code Using a Continuous-energy Monte
Carlo Code MVP
Draft report for JAEA-Data/Code (28 Jan. 2005) (in English and Japanese)
NEA-1673/02, included references:
- Y. Nagaya, K. Okumura, T. Mori and M. Nakagawa:MVP/GMVP II : General Purpose Monte Carlo Codes for Neutron and Photon
Transport Calculations based on Continuous Energy and Multigroup Methods
JAERI-1348 (2005)
- K. Okumura, Y. Nagaya and T. Mori:
MVP-BURN: Burn-up Calculation Code Using a Continuous-energy Monte
Carlo Code MVP
Draft report for JAEA-Data/Code (28 Jan. 2005) (in English and Japanese)
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| Package ID | Computer language |
|---|---|
| NEA-1673/01 | C-LANGUAGE, FORTRAN-77 |
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13. SOFTWARE REQUIREMENTS
MVP/GMVP runs under various UNIX operating systems.
Sun : SunOS4.x/SunOS5.x (Solaris 2.x)
HP : HP-UX9.x/10.x/11.x, Tru UNIX (DEC/OSF1)
IBM : AIX
SGI : IRIX5.x/6.x
NEC : SUPER-UX
Fujitsu : Solaris 2.x, UXP/V
Cray : UNICOS
Hitachi : HI-OSF, HI-UX
MIPS : RISC/OS
Intel : OSF1
MVP/GMVP runs on PC's running the following operating systems: Linux, FreeBSD, Solaris2.x, MS-Windows, CYGWIN on MS-Windows.
MVP/GMVP runs under various UNIX operating systems.
Sun : SunOS4.x/SunOS5.x (Solaris 2.x)
HP : HP-UX9.x/10.x/11.x, Tru UNIX (DEC/OSF1)
IBM : AIX
SGI : IRIX5.x/6.x
NEC : SUPER-UX
Fujitsu : Solaris 2.x, UXP/V
Cray : UNICOS
Hitachi : HI-OSF, HI-UX
MIPS : RISC/OS
Intel : OSF1
MVP/GMVP runs on PC's running the following operating systems: Linux, FreeBSD, Solaris2.x, MS-Windows, CYGWIN on MS-Windows.
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NEA-1673/01
@ReadMe.txt : Description for MVP/GMVP code packageReadme_win32_en.txt : Description for Windows version of MVP/GMVP in English
Readme_win32_jp.txt : Description for Windows version of MVP/GMVP in Japanese
mvp2.0.tar.gz : Archive file of MVP/GMVP II
mvp2.0binwin.zip : Archive file of executables for MVP, GMVP, etc
man_MVP : Users' manual of MVP/GMVP, MVP-BURN codes
MVPlib : MVP libraries (JENDL-3.3, photon, electron, dosimetry) in binary
ReadMVP.tar.gz : Archive file for an edit program from MVP binary output to
produce tables of spectrum, reaction rates and so on in a text file for Excel
etc
PDS : Public domain software on DOS
ICSBEP : Sample MVP input/output data
MVPlib : MVP libraries (JENDL-3.2, ENDF/B-VI.8) in binary form
MVPlib : MVP libraries (JEF-3.0, JEF-2.2) in binary form
NEA-1673/02
@ReadMe.txt : Description for MVP/GMVP code package.mvp2.0.tar.gz : Archive file of MVP/GMVP II.
mvp2.0binwin.zip : Archive file of executables for MVP, GMVP, etc.
man_MVP : Users' manual of MVP/GMVP, MVP-BURN codes.
MVPlib : MVP libraries in the text form and shell scripts or batch files to
convert into the binary form.
ReadMVP.tar.gz : Archive file for an edit program from MVP binary output to
produce tables of spectrum, reaction rates and so on in a text file for Excel
etc.
PDS : Public domain software on DOS.
ICSBEP : Sample MVP input/output data based on International Criticality Safety
Benchmark Evaluation Project.
@ReadMe+.txt : Description for additional MVP libraries.
MVPlib_J32 : MVP JENDL-3.2 libraries in the text form and shell scripts or batch
files to convert into the binary form.
MVPlib_B68 : MVP ENDF/B-VI.8 libraries in the text form and shell scripts or
batch files to convert into the binary form.
MVPlib_F30 : MVP JEF-3.0 libraries in the text form and shell scripts or batch
files to convert into the binary form.
MVPlib_F22MVP JEF-2.2 libraries in the text form and shell scripts or batch
files to convert into the binary form.
Keywords: Monte Carlo method, continuous energy, criticality, multigroup, neutron transport, photon transport.