NEA-1732 3D-TRANS-2003.

3D-TRANS-2003, Workshop on Common Tools and Interfaces for Radiation Transport Codes

NAME, COMPUTER, PROBLEM, AUXILIARIES, STATUS, REFERENCES, LANGUAGE, AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM

3D-TRANS-2003.

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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
3D-TRANS-2003	NEA-1732/02	Tested	14-DEC-2004

Machines used:

Package ID	Orig. computer	Test computer
NEA-1732/02	Many Computers	Many Computers

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3. DESCRIPTION OF PROGRAM OR FUNCTION

Contents proceedings of Workshop on Common Tools and Interfaces for Deterministic Radiation Transport, for Monte Carlo and Hybrid Codes with a proposal to develop the following:

GERALD - A General Environment for Radiation Analysis and Design

GERALD intends to create a unifying software environment where the user can define, solve and analyse a nuclear radiation transport problem using available numerical tools seamlessly. This environment will serve many purposes: teaching, research, industrial needs. It will also help to preserve the existing analytical and numerical knowledge base. This could represent a significant step towards solving the legacy problem. This activity should contribute to attracting young engineers to nuclear science and engineering and contribute to competence and knowledge preservation and management. This proposal was made at the on Workshop on "Common Tools and Interfaces for Deterministic Radiation Transport, for Monte Carlo and Hybrid Codes", held from 25-26 September 2003 in connection with the conference SNA-2003. A first success with the development of such tools was achieved with the BOT3P2.0 and 3.0 codes providing an easy procedure and mechanism for defining and displaying 3D geometries and materials both in the form of refineable meshes for deterministic codes or Monte Carlo geometries consistent with deterministic models.

Advanced SUSD - Improved tools for Sensitivity/Uncertainty Analysis

The development of tools for the analysis and estimation of sensitivities and uncertainties in calculations, or their propagation through complex computational schemes, in the field of neutronics, thermal hydraulics and also thermo-mechanics is of increasing importance for research and engineering applications. These tools allow establishing better margins for engineering designs and for the safe operation of nuclear facilities. Such tools are not sufficiently developed, but their need is increasingly evident in many activities.

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8. RELATED OR AUXILIARY PROGRAMS

NEA-1678: BOT3P4.1, 3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results
CCC-0650: DOORS, Discrete-Ordinates System for Deep-Penetration Neutron and Gamma Transport
NEA-1708: ADEFTA 1.0, Atomic Densities for Transport Analysis
CCC-0547: TWODANT-SYS, DANTSYS3.0, 1-D, 2-D MultiGroup Discrete Ordinate Method Transport

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9. STATUS

Package ID	Status date	Status
NEA-1732/02	14-DEC-2004	Screened

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10. REFERENCES

NEA-1732/02, included references:

- Elmer Lewis:
Applying adaptive grid techniques for radiation problems with
large numbers of material interfaces and need for refining the angular and
energy approximations in ways consistent with spatial refinements.
- Cassiano R E de Oliveira, Christopher Pain, Matthew Eaton and Gerard Gorman:
Unstructured mesh radiation transport methods : overview, trends and challenges
- Petri Kotiluoto:
3-D radiation transport code (based on tree multigrid technique and SP3
approximation), which has a CAD-interface for automatic mesh generation
- Christian Aussourd:
Styx 3D Modeling Chain - Past, Present and Future
- Alireza Haghighat:
Performing 3-D Multigroup SN Transport Calculations in the 21st Century
- I.R.Suslov:
An MCCG3D - A 3-D Characteristics Code. An Overview
- Robert Roy:
Designing new software tools for CANDU analysis
- Alireza Haghighat:
Use of Deterministic importance function for variance reduction of Monte Carlo
- Lev Tocheny:
Development and Verification of Radiation Transport Codes through ISTC Projects
- Roberto Orsi:
The BOT3P Tool and ADEFTA for material characterisation
- Yoshihiro HIRAO, Makoto MORISHIMA:
Development of an Input-Making Support System for a DORT-TORT Code
- Forrest Brown: MCNP Visualization
- Kenneth A. Van Riper:
Mesh and Volume Fraction Capabilities in Moritz
- Chang Hyo KIM:
"Hierarchical Geometry Input Routines of MC-CARD" 3D meshing of a reactor
system
- Cassiano de Oliveira:
EVENT & RADIANT - Creating a general purpose environment for the analysis of
radiation problems
- Richard Sanchez, Zarko Stankovski:
3D radiation transport tools and issues at CEA
- Ivo Kodeli:
Needs for 3D Sensitivity and Uncertainty Analysis (OECD/NEA)
- Philippe Humbert:
3D Benchmarks with Panda Code.
- Siegfried Langenbuch, Armin Seubert, Winfried Zwermann:
Experience with deterministic and Monte Carlo methods for 3D criticality
benchmarks.
- Adrien Bideau, Victor Mastrangelo:
Results of Benchmarks carried out with DANTSYS, DOORS and BOT3P3
- Mikhail Ternovykh, Georgyi Tikhomirov:
"Education in nuclear area and transport codes".
- Yousry Azmy:
Proposal for DORT/TORT Users Group (DTUG).and Proposal for a Virtual Institute
for Computational Transport Theory

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12. PROGRAMMING LANGUAGE(S) USED

No specified programming language

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15. NAME AND ESTABLISHMENT OF AUTHORS

OECD NEA Databank
Le Seine Saint-Germain
12, boulevard des Iles
92130 Issy-les-Moulineaux

FRANCE

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16. MATERIAL AVAILABLE

NEA-1732/02

Proceedings of the 3D-TRANS-2003, Workshop on Common Tools and Interfaces for
Deterministic Radiation Transport, for Monte Carlo and Hybrid Codes.
Paris 25-26 September 2003 (PDF format)

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17. CATEGORIES