Computer Programs
NEA-1905 MORET 5.D.1.
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NEA-1905 MORET 5.D.1.

MORET 5.D.1, Monte Carlo simulation tool to solve transport equation for neutrons

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1. NAME OR DESIGNATION OF PROGRAM

MORET 5.D.1.

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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
MORET 5.D.1 NEA-1905/01 Tested 15-MAY-2019

Machines used:

Package ID Orig. computer Test computer
NEA-1905/01 Linux-based PC Linux-based PC
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Initially designed to perform calculations to support criticality safety assessments, the MORET code is a Monte Carlo simulation tool that solves the transport equation for neutrons. From its inception, the code has been constructed with the aim of providing a great flexibility to implement new components or methods without any difficulties. The result is a code that allows users to model complex three-dimensional geometrical configurations, use various evaluations and treatments for nuclear data to describe the materials, select the best adapted simulation method (from all methods available) related to their problem, define their own tallies and analyse the results.

 

Geometry modelling

 

The description of the geometry relies on combinatorial geometry for which user has to create volumes that will contain the materials. Operators may be added to describe the combinatorial properties of the volumes. The code gives the possibility of defining the geometry as a composition of several regions. This modular geometry allows to model complex geometries by using basic building blocks, called "modules". These parts of the whole geometry can be embedded one in another using "holes". A geometry-plotting function is available to display the modeling.

 

Description of materials

 

The MORET code allows two calculation routes for the treatment of the cross sections energy dependence: multi-group approach (with direct use of macroscopic cross section sets, which result from preliminary cell code calculations), and continuous energy calculations using the nuclear data libraries included in this distribution.

 

Simulation and neutron tracking

 

The Monte Carlo simulation consists of simulating a number of individual neutrons by reproducing as accurately as possible their elementary behaviour. It is an iterative process, following neutrons from their birth until death (whatever the cause). For each cycle, the new neutron distribution is defined based on fissions generated in the previous one. The MORET code embeds several techniques for tracking (such as the Woodcock method) and sampling source neutrons among potential fission sites to address two concerns: force neutrons to visit all fissile volumes to reduce the risk of weak coupling, and accelerate the source convergence. The sampling methods are the analogue method, the stratified sampling, the fission matrix method, the importance method, the oversampling method, the superhistory powering and the Wielandt method.

 

Nuclear data

 

The nuclear data distribution consists in continuous-energy nuclear data libraries in ACE format. These nuclear data libraries were all generated using NJOY 99.259 using the same reconstruction tolerances (0.1 0 %).

These nuclear data libraries are based on JEFF 3.1.1 and ENDF/B-VII.0 nuclear data evaluations and are available at various temperatures: 293.6, 300, 600, 900, 1200, 1500 and 1800 K.

The JEFF 3.1.1 and ENDF/B-VII.0 data libraries also have S(α,β) ACE files associated to them for a number of materials: H in H20, H in CH2, Be metal, Be in BeO and graphite.

 

The following nuclides and elements are available (for the given evaluation source):

 

JEFF 3.1.1:

 

H1, H2, H3, HE3, HE4, LI6, LI7, BE9, B10, B11, C, N14, N15, O16, O17, F19, NA22, NA23, MG24, MG25, MG26, AL27, SI28, SI29, SI30, P31, S32, S33, S34, S36, CL35, CL37, AR36, AR38, AR40, K39, K40, K41, CA40, CA42, CA43, CA44, CA46, CA48, SC45, TI46, TI47, TI48, TI49, TI50, V, CR50, CR52, CR53, CR54, MN55, FE54, FE56, FE57, FE58, C058, C058M, C059, NI58, NI59, NI60, NI6I, NI62, NI64, CU63, CU65, ZN, GA, GE70, GE72, GE73, GE74, GE76, AS75, SE74, SE76, SE77, SE78, SE79, SE80, SE82, BR79, BR81, KR78, KR80, KR82, KR83, KR84, KR85, KR86, RB85, RB86, RB87, SR84, SR86, SR87, SR88, SR89, SR90, Y89, Y90, Y91, ZR90, ZR91, ZR92, ZR93, ZR94, ZR95, ZR96, NB93, NB94, NB95, MO92, MO94, MO95, MO96, MO97, MO98, MO99, MO100, TC99, RU96, RU98, RU99, RU100, RU101, RU102, RU103, RU104, RU105, RU106, RH103, RH105, PD102, PD104, PD105, PD106, PD107, PD108, PD110, AG107, AG109, AG110M, AG111, CD106, CD108, CD110, CD111, CD112, CD113, CD114, CD115M, CD116, IN113, IN115, SN112, SN114, SN115, SN116, SN117, SN118, SN119, SN120, SN122, SN123, SN124, SN125, SN126, SB121, SB123, SB124, SB125, SB126, TE120, TE122, TE123, TE124, TE125, TE126, TE127M, TE128, TE129M, TE130, TE132, I127, I129, I130, I131, I135, XE124, XE126, XE128, XE129, XE130, XE131, XE132, XE133, XE134, XE135, XE136, CS133, CS134, CS135, CS136, CS137, BA130, BA132, BA134, BA135, BA136, BA137, BA138, BA140, LA138, LA139, LA140, CE140, CE141, CE142, CE143, CE144, PR141, PR142, PR143, ND142, ND143, ND144, ND145, ND146, ND147, ND148, ND150, PM147, PM148, PM148M, PM149, PM151, SM144, SM147, SM148, SM149, SM150, SM151, SM152, SM153, SM154, EU151, EU152, EU153, EU154, EU155, EU156, EU157, GD152, GD154, GD155, GD156, GD157, GD158, GD160, TB159, TB160, DY160, DY161, DY162, DY163, DY164, HO165, ER162, ER164, ER166, ER167, ER168, ER170, LU175, LU176, HF174, HF176, HF177, HF178, HF179, HF180, TA181, TA182, W182, W183, W184, W186, RE185, RE187, OS, IR191, IR193, PT, AU197, HG196, HG198, HG199, HG200, HG201, HG202, HG204, TL, PB204, PB206, PB207, PB208, BI209, RA223, RA224, RA225, RA226, AC225, AC226, AC227, TH227, TH228, TH229, TH230, TH232, TH233, TH234, PA231, PA232, PA233, U232, U233, U234, U235, U236, U237, U238, NP235, NP236, NP237, NP238, NP239, PU236, PU237, PU238, PU239, PU240, PU241, PU242, PU243, PU244, PU246, AM241, AM242, AM242M, AM243, AM244, AM244M, CM240, CM241, CM242, CM243, CM244, CM245, CM246, CM247, CM248, CM249, CM250, BK247, BK249, BK250, CF249, CF250, CF251, CF252, CF254,ES253,ES254,ES255,FM255.

 

ENDF/B-VII.0:

 

H1, H2, H3, HE3, HE4, LI6, LI7, BE7, BE9, B10, B11, C, N14, N15, O16, O17, F19, NA22, NA23, MG24, MG25, MG26, AL27, S128, S129, S130, P31, S32, S33, S34, S36, CL35, CL37, AR36, AR38, AR40, K39, K40, K41, CA40, CA42, CA43, CA44, CA46, CA48, SC45, TI46, TI47, TI48, TI49, TI50, V, CR50, CR52, CR53, CR54, MN55, FE54, FE56, FE57, FE58, C058, C058M, C059, NI58, NI59, NI60, NI6I, NI62, NI64, CU63, CU65, ZN, GA69, GA71, GE70, GE72, GE73, GE74, GE76, AS74, AS75, SE74, SE76, SE77, SE78, SE79, SE80, SE82, BR79, BR81, KR78, KR80, KR82, KR83, KR84, KR85, KR86, RB85, RB86, RB87, SR84, SR86, SR87, SR88, SR89, SR90, Y89, Y90, Y91, ZR90, ZR91, ZR92, ZR93, ZR94, ZR95, ZR96, NB93, NB94, NB95, MO92, MO94, MO95, MO96, MO97, MO98, MO99, MO100, TC99, RU96, RU98, RU99, RU100, RU101, RU1022, RU103, RU104, RU105, RU106, RH103, RH105, PD102, PD104, PD105, PD106, PD107, PD108, PD110, AG107, AG109, AG110M, AG111, CD106, CD108, CD110, CD111, CD112, CD113, CD114, CD115M, CD116, IN113, IN115, SN112, SN113, SN114, SN115, SN116, SN117, SN118, SN119, SN120, SN122, SN123, SN124, SN125, SN126, SB121, SB123, SB124, SB125, SB126, TE120, TE122, TE123, TE124, TE125, TE126, TE127M, TE128, TE129M, TE130, TE132, I127, I129, I130, I131, I135, XE123, XE124, XE126, XE128, XE129, XE130, XE131, XE132, XE133, XE134, XE135, XE136, CS133, CS134, CS135, CS136, CS137, BA130, BA132, BA133, BA134, BA135, BA136, BA137, BA138, BA140, LA138, LA139, LA140, CE136, CE138, CE139, CE140, CE141, CE142, CE143, CE144, PR141, PR142, PR143, ND142, ND143, ND144, ND145, ND146, ND147, ND148, ND150, PM147, PM148, PM148M, PM149, PM151, SM144, SM147, SM148, SM149, SM150, SM151, SM152, SM153, SM154, EU151, EU152, EU153, EU154, EU155, EU156, EU157, GD152, GD153, GD154, GD155, GD156, GD157, GD158, GD160, TB159, TB160, DY156, DY158, DY160, DY161, DY162, DY163, DY164, HO165, HO166M, ER162, ER164, ER166, ER167, ER168, ER170, LU175, LU176, HF174, HF176, HF177, HF178, HF179, HF180, TA181, TA182, W182, W183, W184, W186, RE185, RE187, IR191, IR193, AU197, HG196, HG198, HG199, HG200, HG201, HG202, HG204, PB204, PB206, PB207, PB208, BI209, RA223, RA224, RA225, RA226, AC225, AC226, AC227, TH227, TH228, TH229, TH230, TH232, TH233, TH234, PA231, PA232, PA233, U232, U233, U234, U235, U236, U237, U238, U239, U240, U241, NP235, NP236, NP237, NP238, NP239, PU236, PU237, PU238, PU239, PU240, PU241, PU242, PU243, PU244, PU246, AM241, AM242, AM242M, AM243, AM244, AM244M, CM241, CM242, CM243, CM244, CM245, CM246, CM247, CM248, CM249, CM250, BK249, BK250, CF249, CF250, CF251, CF252, CF253, CF254, ES253, ES254, ES255, FM255

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4. METHODS

The MORET code is a simulation tool that solves the Bolzmann's equation using the Monte Carlo method. It transports neutrons with energies in the range of 10-5 eV to 150 MeV (energy ranges are limited by the available cross section sets and physics models).

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The resolution of any problem with a very large number of volumes and/or material compositions may be limited by the computer memory. Modeling assumptions that limit the memory consumption are discussed in the included documentation.

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6. TYPICAL RUNNING TIME

The calculation time depends on the complexity and required precision for a given case. It depends on the complexity of geometry modelling, the number of material compositions, and the number of particles to be simulated. For a very precise solution, a few hours of computation may be necessary, depending on the speed of the machine.

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9. STATUS
Package ID Status date Status
NEA-1905/01 15-MAY-2019 Tested restricted
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10. REFERENCES

Background documentation:

  • Alexis Jinaphanh, Nicolas Leclaire, Bertrand Cochet: "Continuous-energy sensitivity coefficients in the MORET code", Nuclear Science and Engineering, 184, pp 53-68 (2016)

  • N. Leclaire, B. Cochet, F.X. Le Dauphin, W. Haeck, 0. Jacquet: "Use of the ETA-1 reactor for the validation of the multi-group APOLL02-MORET 5 code and the Monte Carlo continuous energy MORET 5 code", Annals of Nuclear Energy, 76, pp 530-539 (2015}

  • B. Cochet, A. Jinaphanh, L. Heulers, 0. Jacquet: "Capabilities overview of the MORET 5 Monte Carlo code", Annals of Nuclear Energy, 82, pp 74-84 (2015)

NEA-1905/01, included references:
- B. Cochet and A. Jinaphanh:
"MORET User's Manual- Version 5.D.1 ", IRSN PSN-EXP/SNC/2017-282, Institut de
Radioprotection et de Surete Nucleaire, France (20 17)
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11. HARDWARE REQUIREMENTS

Supported platforms are PC and Workstations/Clusters running Linux OS.

The MORET code system requires 15 MB of disk space. The associated nuclear data libraries require 20 GB.

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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1905/01 C-LANGUAGE, FORTRAN
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13. SOFTWARE REQUIREMENTS

This distribution contains executables for Linux systems, nuclear data libraries, test cases and documentation. NO SOURCES ARE INCLUDED.

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

MORET can be launched using a python 2. 7 script included in this distribution.

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15. NAME AND ESTABLISHMENT OF AUTHORS

B. COCHET, A. JINAPHANH

IRSN

BP 17

92262 Fontenay-Aux-Roses Cedex

FRANCE

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16. MATERIAL AVAILABLE
NEA-1905/01
Executables for Linux systems (no sources are included)
Nuclear data in ENDF and ACE format: 2 libraries based on JEFF 3.1.1 and
ENDF/B-VII.O evaluations
Test cases
Scripts
Installation procedure (README files)
Electronic documentation
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17. CATEGORIES
  • C. Static Design Studies

Keywords: Monte Carlo simulation, continuous energy calculations, criticality safety, neutron 3D geometry modelling, particle transport, reactor physics.