Computer Programs
NEA-1673 MVP/GMVP V.3
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NEA-1673 MVP/GMVP V.3

MVP/GMVP V.3, MC Codes for Neutron & Photon Transport Calc. based on Continuous Energy and Multigroup Methods

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1. NAME OR DESIGNATION OF PROGRAM

MVP/GMVP Version 3.

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
MVP/GMVP V.3 NEA-1673/04 Tested 21-FEB-2019

Machines used:

Package ID Orig. computer Test computer
NEA-1673/04 Linux-based PC,PC Windows,UNIX W.S. Linux-based PC,PC Windows
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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
Energy-, angle-, space- and time-dependent particle sources can be specified with various sampling functions.

 

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-4.0, ENDF/B-VII.1, JEFF-3.2 etc.) by using the LICEM code. The neutron cross sections in the unresolved resonance region are described with 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 analogue 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.

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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(α,β) 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 with 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 table lists CPU times for sample problems.  All the calculations were performed on Linux with a single core of Intel Xeon CPU E5-2630, 2.30 GHz.

 

MVP

sample1 (Single assembly calculation):  2 min 14 sec

sample2 (Four assembly calculation):  57 sec

sample3 (Neutron-photon coupled problem):  3 min 20 sec

sample4 (Example of the statistical geometry model):  1 min 53 sec

sample5 (Example of the FREE-FRAME-LATTICE option):  37 sec

sample6 (Example of tally dimensions SOURCE-REGION and MARKER-REGION):  10 sec

sample7 (Example of a Feynman-alpha calculation):  29 sec

sample8 (Example of surface crossing and collision estimators):  14 sec

sample9 (Example of surface crossing and point estimators):  11 sec

 

GMVP

sample1 (Takeda benchmark):  7 sec

sample2 (Calculation with the DDX-form cross sections):  1 sec

sample3 (Neutron-photon coupled problem):  16 sec

sample4 (Example of the statistical geometry model):  27 sec

sample5 (Example of the FREE-FRAME-LATTICE option):  40 sec

sample6 (Example of tally dimensions SOURCE-REGION and MARKER-REGION):  5 sec

sample7 (Example of a Feynman-alpha calculation):  6 sec

sample8 (Example of surface crossing and collision estimators):  11 sec

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7. UNUSUAL FEATURES OF THE PROGRAM

MVP/GMVP has the following unusual capabilities:

  • Burnup calculation with the MVP-BURN code.

  • Reactor noise analysis based on simulation of Feynman-alpha experiments.

  • Statistical geometry model is available to address the heterogeneity of coated fuel particles or pebbles for high temperature gas-cooled reactors.

 

MVP Version 3 implements the following new capabilities:

  • Perturbation calculation for effective multiplication factor.

  • Exact resonant elastic scattering model.

  • Calculation of reactor kinetics parameters (effective delayed neutron fraction and neutron generation time).

  • Photonuclear reaction model.

  • Simulation of delayed neutrons.

  • Generation of group constants.

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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.

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9. STATUS
Package ID Status date Status
NEA-1673/04 21-FEB-2019 Tested at NEADB
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10. REFERENCES
  • Yasunobu NAGAYA, Keisuke OKUMURA, Takeshi SAKURAI and Takamasa MORI, “MVP/GMVP Version 3: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods,” JAEA-Data/Code 2016-019 (2017) [in Japanese] DOI:10.11484/jaea-data-code-2016-019.

  • Yasunobu NAGAYA, Keisuke OKUMURA, Takeshi SAKURAI and Takamasa MORI, “MVP/GMVP Version 3: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods (Translated document),” JAEA-Data/Code 2016-018 (2017) [in English] DOI:10.11484/jaea-data-code-2016-018.

 

NEA-1673/04, included references:
- Yasunobu NAGAYA, Keisuke OKUMURA, Takeshi SAKURAI and Takamasa MORI:
MVP/GMVP Version 3: General Purpose Monte Carlo Codes for Neutron and Photon
Transport Calculations Based on Continuous Energy and Multigroup Methods,
JAEA-Data/Code 2016-018
DOI:10.11484/jaea-data-code-2016-018

-Yasunobu NAGAYA, Keisuke OKUMURA, Takeshi SAKURAI and Takamasa MORI:
MVP/GMVP Version 3: General Purpose Monte Carlo Codes for Neutron and Photon
Transport Calculations Based on Continuous Energy and Multigroup Methods (in
Japanese), JAEA-Data/Code 2016-019
DOI:10.11484/jaea-data-code-2016-019

- Keisuke OKUMURA, Yasunobu NAGAYA, Takamasa MORI:
MVP-BURN: Burn-up Calculation Code Using a Continuous-energy Monte Carlo Code
MVP, Draft report for JAEA-Data/Code (to be submitted in 2006), Last update 28
Jan. 05 (in English and in Japanese)

- Yasunobu Nagaya, Keisuke Okumura, Takamasa Mori:
Recent developments of JAEA's Monte Carlo code MVP for reactor physics
applications (Annals of Nuclear Energy 82 (2015) 85-89, 2014)

- Yasunobu Nagaya, Keisuke Okumura, and Takamasa Mori:
Recent Developments of JAEA's Monte Carlo Code MVP for Reactor Physics
Applications (Joint International Conference on Supercomputing in Nuclear
Applications and Monte Carlo 2013 (SNA + MC 2013) La Cite des Sciences et de
l'Industrie, Paris, France, October 27-31, 2013)

- Yasunobu NAGAYA, Keisuke OKUMURA, Takamasa MORI:
MVP Version 3: A General-Purpose Monte Carlo Code for Continuous-Energy Neutron
and Photon Transport Calculations (Joint International Conference on
Mathematics & Computation, Supercomputing in Nuclear Applications and the Monte
Carlo Method (M&C+SNA+MC 2015), Nashville, Tennessee, USA, April 19-23, 2015)
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11. HARDWARE REQUIREMENTS

MVP/GMVP runs on various platforms such as standard PCs, Mac or UNIX workstations. Disk space of about 80 Mbytes is required to make the executables from the program sources. A large amount of disk space is required for the cross section data of the MVP code. To install the cross section libraries for MVP (MVP libraries), disk space of about 1.1 Gbytes is required for JENDL-4.0. Doubled disk space is necessary for the 64-bit version of MVP (more than 2 Gbytes of memory is usable).

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1673/04 C-LANGUAGE, FORTRAN-77
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13. SOFTWARE REQUIREMENTS

MVP/GMVP runs on the following operating systems: Linux, FreeBSD, Solaris2.x, MS-Windows, CYGWIN. The following Fortran/C compilers are supported: Intel compliers, GNU compilers and Fujitsu compilers.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Dynamic memory allocation is available if compilers support Cray-pointers. The upper limit of the usable memory size is 2 Gbytes if MVP/GMVP is compiled with the 32-bit mode.

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15. NAME AND ESTABLISHMENT OF AUTHORS

Yasunobu NAGAYA, Keisuke OKUMURA, Takeshi SAKURAI and Takamasa MORI

Research Group for Reactor Physics and Standard Nuclear Code System

Nuclear Data and Reactor Engineering Division

Nuclear Science and Engineering Center

Japan Atomic Energy Agency

Tokai-mura, Naka-gun, Ibaraki

Japan

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16. MATERIAL AVAILABLE
NEA-1673/04
* mvp3.0.tar.gz: Archive file of MVP source codes (Version 3.0).
* SetupMVP.msi: MSI installer for Windows.
* MVP3BASE.cab: Archive file of MVP windows binary.
* man_MVP/ : Directory for users manuals
- JAEA-Data-Code-2016-018.pdf : Users' manual of the MVP/GMVP system (in
English).
- JAEA-Data-Code-2016-018-appendix(CD-ROM).zip : Appendix of
JAEA-Data-Code-2016-018.pdf.
- JAEA-Data-Code-2016-018-hyperlink.zip : Manual with hyperlinks.
- JAEA-Data-Code-2016-019.pdf : Users' manual of the MVP/GMVP system (in
Japanese)
- JAEA-Data-Code-2016-019-hyperlink.zip : Manual with hyperlinks.
- man_mvpburn_051011E.pdf  : Users' manual of the MVP-BURN code (in English)
- man_mvpburn_051011jp.pdf : Users' manual of the MVP-BURN code (in Japanese)
- ANE.82.85-89.pdf
- SNAMC2013.MvpStatus2013.r1.pdf
- SNAMC2015.MVP3_nagaya.r1.pdf
* MVPlib/ : Directory for MVP libraries: JENDL-4.0 neutron library, photoatomic
library, photonuclear library, electron library, dosimetry library.
* MVPlibSup/ : Directory for MVP supplemental libraries: ENDF/B neutron
libraries, JEFF neutron libraries.
* MVPutils/ : MVP utilities.
- ReadMVP.tar.gz : A utility program to read an MVP binary output file.
* ICSBEP: Sample input files for ICSBEP benchmarks.
- input/
- LEU-COMP-THERM-019-002.inp
- LEU-SOL-THERM-004-001.inp
- MIX-COMP-THERM-004-001.inp
- outp/
- LEU-COMP-THERM-019-002.ft06
- LEU-SOL-THERM-004-001.ft06
- MIX-COMP-THERM-004-001.ft06
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17. CATEGORIES
  • C. Static Design Studies
  • J. Gamma Heating and Shield Design

Keywords: Monte Carlo method, continuous energy, criticality, multigroup, neutron transport, photon transport.