Refine your search:     
Report No.
 - 
Search Results: Records 1-4 displayed on this page of 4
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Large Eddy Simulation of highly-fluctuational temperature and velocity fields observed in a mixing-tee experiment

Coste, P.*; Quemere, P.*; Roubin, P.*; Emonot, P.*; Tanaka, Masaaki; Kamide, Hideki

Nuclear Technology, 164(1), p.76 - 88, 2008/10

 Times Cited Count:12 Percentile:61.74(Nuclear Science & Technology)

The WATLON experiment, a water facility about fluid mixing in a T-pipe, is calculated with a finite element volume method and a Large Eddy Simulation (LES) approach, with TRIO-U code. Its unstructured tetrahedron grids do not lead to the same noteworthy disagreements previously mentioned with Cartesian grids. Branch and main pipe inlet velocity fluctuations due to turbulence are simulated with the use of "periodic boxes". These more realistic inlet fluctuations allow physical instabilities to develop, improving the predictions. When an elbow is added upstream of the injection, the influence of the secondary flow on temperature averaged values and fluctuations is underlined.

Journal Articles

Large eddy simulation of a mixing-T experiment

Coste, P.*; Quemere, P.*; Roubin, P.*; Emonot, P.*; Tanaka, Masaaki; Kamide, Hideki

Proceedings of 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06) (CD-ROM), p.1626 - 1635, 2006/06

The WATLON experiment, a water facility about fluid mixing in a T-pipe, is calculated with a finite element volume method and a Large Eddy Simulation (LES) approach, with TRIO-U code. Its unstructured tetrahedron grids do not lead to the same noteworthy disagreements previously mentioned with Cartesian grids. Branch and main pipe inlet velocity fluctuations due to turbulence are simulated with the use of "periodic boxes". These more realistic inlet fluctuations allow physical instabilities to develop, improving the predictions. When an elbow is added upstream of the injection, the influence of the secondary flow on temperature averaged values and fluctuations is underlined.

Journal Articles

The Development of SIMMER-III, an advanced computer program for LMFR safety analysis, and its application to sodium experiments

Tobita, Yoshiharu; Kondo, Satoru; Yamano, Hidemasa; Morita, Koji*; Maschek, W.*; Coste, P.*; Cadiou, T.*

Nuclear Technology, 153(3), p.245 - 255, 2006/03

 Times Cited Count:75 Percentile:97.56(Nuclear Science & Technology)

SIMMER-III is a general two-dimensional, three-velocity-field, multiphase, multicomponent, Eulerian, fluid-dynamics code coupled with a space-time and energy-dependent neutron transport kinetics model. The philosophy behind the SIMMER development was to generate a versatile and flexible tool, applicable for the safety analysis of various reactor types with different neutron spectra and coolants, up the new accelerator driven systems (ADS) for waste transmutation. SIMMER-III has proven especially well suited for fast spectrum systems as the LMFR, where it is one of the key codes for safety analysis, including its application within licensing procedures. To serve especially the last purpose, the code must be made sufficiently robust and reliable, and be tested and validated extensively. A comprehensive and systematic assessment program of the code has been conducted. This paper gives the major achievement of this assessment program. The code assessment program is an ongoing effort. Two major milestones have been achieved in the past by completing two assessment campaigns, Phase 1 and Phase 2. Phase 1 for fundamental code assessment of individual models; and Phase 2 for integral code assessment for key phenomena relevant to LMFR safety. Through this systematic code assessment program, comprehensive validation of the physical models has been conducted step-by-step. The assessment program has demonstrated that SIMMER-III is a state-of-the-art code with advanced models sufficiently flexible for simulating transient multiphase phenomena occurring during CDAs. In this paper we will concentrate on the specifics of the code, mainly reflected at its application to sodium experiments related to the safety of LMFR.

JAEA Reports

SIMMER-III: A Computer Program for LMFR Core Disruptive Accident Analysis; Version 3.A Model Summary and Program Description

Yamano, Hidemasa; Fujita, Satoshi; Tobita, Yoshiharu; Kamiyama, Kenji; Kondo, Satoru; Morita, Koji*; Fischer, E. A.; Brear, D. J.; Shirakawa, Noriyuki*; Cao, X.; et al.

JNC TN9400 2003-071, 340 Pages, 2003/08

JNC-TN9400-2003-071.pdf:1.54MB

An advanced safety analysis computer code, SIMMER-III, has been developed to investigate postulated core disruptive accidents in liquid-metal fast reactors (LMFRs). SIMMER-III is a two-dimensional, three-velocity-field, multiphase, multicomponent, Eulerian, fluid-dynamics code coupled with a space-dependent neutron kinetics model. By completing and integrating all the physical models originally intended at the beginning of this code development project, SIMMER-III is now applicable to integral reactor calculations and other complex multiphase flow problems. A systematic code assessment program, conducted in collaboration with European research organizations, has shown that the advanced features of the code have resolved many of the limitations and problem areas in the previous SIMMER-II code. In this report, the models, numerical algorithms and code features of SIMMER-III Version 3.A are described along with detailed program description. Areas which require future model refinement are also discussed. SIMMER-III Version 3.A, a coupled fluid-dynamics and neutronics code system, is expected to significantly improve the flexibility and reliability of LMFR safety analyses.

4 (Records 1-4 displayed on this page)
  • 1