Verification of multiTrans calculations by the VENUS-3 benchmark experiment

Research output: Contribution to journalArticleScientificpeer-review

1 Citation (Scopus)

Abstract

The MultiTrans software has been developed at VTT Technical Research Centre of Finland for 3D radiation transport problems. Adaptive tree multigrid technique is used as a deterministic solution method. This enables local refinement of the calculation grid combined with the use of effective multigrid acceleration on tree-structured nested grids: starting from a fast solution on coarse grid, successive solutions are obtained on finer and finer grids. In the MultiTrans code, simplified spherical harmonics (SP3) radiation transport approximation is used. In order to test the applicability of the new MultiTrans code to reactor dosimetry problems, light water reactor pressure vessel steel (LWR-PVS) benchmark experiment VENUS-3 (with partial length shielded assemblies) was chosen. The results show good agreement to the experimental reaction rates of the VENUS-3 benchmark, demonstrating the applicability of the new MultiTrans code in reactor dosimetry.

Original languageEnglish
Number of pages6
JournalJournal of ASTM International
Volume3
Issue number3
DOIs
Publication statusPublished - 2006
MoE publication typeA1 Journal article-refereed

Fingerprint

Benchmarking
Dosimetry
Radiation
Light water reactors
Steel
Steel structures
Finland
Reaction rates
Software
Experiments
Pressure
Water
Research

Keywords

  • MultiTrans
  • Radiation transport
  • Reactor dosimetry
  • Tree multigrids
  • VENUS-3 benchmark

Cite this

@article{68e65ecbffe741dda2ea80879076a926,
title = "Verification of multiTrans calculations by the VENUS-3 benchmark experiment",
abstract = "The MultiTrans software has been developed at VTT Technical Research Centre of Finland for 3D radiation transport problems. Adaptive tree multigrid technique is used as a deterministic solution method. This enables local refinement of the calculation grid combined with the use of effective multigrid acceleration on tree-structured nested grids: starting from a fast solution on coarse grid, successive solutions are obtained on finer and finer grids. In the MultiTrans code, simplified spherical harmonics (SP3) radiation transport approximation is used. In order to test the applicability of the new MultiTrans code to reactor dosimetry problems, light water reactor pressure vessel steel (LWR-PVS) benchmark experiment VENUS-3 (with partial length shielded assemblies) was chosen. The results show good agreement to the experimental reaction rates of the VENUS-3 benchmark, demonstrating the applicability of the new MultiTrans code in reactor dosimetry.",
keywords = "MultiTrans, Radiation transport, Reactor dosimetry, Tree multigrids, VENUS-3 benchmark",
author = "P. Kotiluoto",
year = "2006",
doi = "10.1520/JAI13433",
language = "English",
volume = "3",
journal = "Journal of ASTM International",
issn = "1546-962X",
publisher = "American Society for Testing and Materials ASTM",
number = "3",

}

Verification of multiTrans calculations by the VENUS-3 benchmark experiment. / Kotiluoto, P.

In: Journal of ASTM International, Vol. 3, No. 3, 2006.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Verification of multiTrans calculations by the VENUS-3 benchmark experiment

AU - Kotiluoto, P.

PY - 2006

Y1 - 2006

N2 - The MultiTrans software has been developed at VTT Technical Research Centre of Finland for 3D radiation transport problems. Adaptive tree multigrid technique is used as a deterministic solution method. This enables local refinement of the calculation grid combined with the use of effective multigrid acceleration on tree-structured nested grids: starting from a fast solution on coarse grid, successive solutions are obtained on finer and finer grids. In the MultiTrans code, simplified spherical harmonics (SP3) radiation transport approximation is used. In order to test the applicability of the new MultiTrans code to reactor dosimetry problems, light water reactor pressure vessel steel (LWR-PVS) benchmark experiment VENUS-3 (with partial length shielded assemblies) was chosen. The results show good agreement to the experimental reaction rates of the VENUS-3 benchmark, demonstrating the applicability of the new MultiTrans code in reactor dosimetry.

AB - The MultiTrans software has been developed at VTT Technical Research Centre of Finland for 3D radiation transport problems. Adaptive tree multigrid technique is used as a deterministic solution method. This enables local refinement of the calculation grid combined with the use of effective multigrid acceleration on tree-structured nested grids: starting from a fast solution on coarse grid, successive solutions are obtained on finer and finer grids. In the MultiTrans code, simplified spherical harmonics (SP3) radiation transport approximation is used. In order to test the applicability of the new MultiTrans code to reactor dosimetry problems, light water reactor pressure vessel steel (LWR-PVS) benchmark experiment VENUS-3 (with partial length shielded assemblies) was chosen. The results show good agreement to the experimental reaction rates of the VENUS-3 benchmark, demonstrating the applicability of the new MultiTrans code in reactor dosimetry.

KW - MultiTrans

KW - Radiation transport

KW - Reactor dosimetry

KW - Tree multigrids

KW - VENUS-3 benchmark

UR - http://www.scopus.com/inward/record.url?scp=33747009899&partnerID=8YFLogxK

U2 - 10.1520/JAI13433

DO - 10.1520/JAI13433

M3 - Article

VL - 3

JO - Journal of ASTM International

JF - Journal of ASTM International

SN - 1546-962X

IS - 3

ER -