Computer Programs

NAME, COMPUTER, PROBLEM, SOLUTION, CPU, FEATURES, AUXILIARIES, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, AUTHOR, MATERIAL, CATEGORIES

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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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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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Package ID | Computer language |
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NEA-1673/04 | C-LANGUAGE, FORTRAN-77 |

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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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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

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