Fast Reactors and Accelerator Driven Systems Knowledge Base

IAEA-TECDOC--1318: Validation of fast reactor thermomechanical and thermohydraulic codes

Final report of a co-ordinated research project 1996-1999

International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC--1318

Abstract

This report is a summary of the work performed under a co-ordinated research project (CRP) entitled Harmonization and Validation of Fast Reactor Thermomechanical and Thermo- Hydraulic Codes and Relations using Experimental Data. The project was organized by the IAEA on the recommendation of the IAEA’s Technical Working Group on Fast Reactors (TWGFR) and carried out from 1996 to 1999.

In certain conditions, temperature fluctuations in the coolant close to a structure caused by thermal striping can lead to thermomechanical damage to structures. Institutes from a number of Member States have an interest in improving engineering tools and prediction techniques concerning the characterization of the thermal striping effects, in which numerical models have a major role. Therefore, the IAEA through its advanced reactor technology development programme supports the activities of Member States in this area. Design analyses applied to thermal striping phenomena need to be firmly established, and the CRP provided a valuable tool in assessing their reliability.

Eleven institutes from France, India, Italy, Japan, the Republic of Korea, the Russian Federation and the United Kingdom co-operated in this CRP.

This report documents the CRP activities, provides the main results and recommendations and includes the work carried out by the research groups at the participating institutes within the CRP on harmonization and validation of fast reactor thermomechanical and thermohydraulic codes and relations.

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Articles

Thermomechanical and thermohydraulic analyses of a T-junction using experimental data
Gelineau, O.; Sperandio, M.; Simoneau, J.P.; Hamy, J.M. (FRAMATOME - NOVATOME, Lyon (France)); Roubin, P.H.L. (CEA DRN SERA, Saint Paul lez Durance (France))

Thermal hydraulics and thermomechanical analysis of thermal striping in a mixing tee-junction of secondary sodium circuit of Phenix reactor
Chellapandi, P.; Velusamy, K.; Biswas, A.; Rama, R.; Bhoje, S.B.; Vaidyanathan, G.; Chetal, S.C. (Indira Gandhi Centre for Atomic Research (IGCAR) (India))

Thermomechanical and fracture mechanics analysis on a tee junction of LMFR secondary circuit due to thermal striping phenomena
Kasahara, N. (O-arai Engineering Center (Japan))

Thermohydraulics computer code system and computational results on thermal striping phenomena at a tee junction of LMFR circuit with the system
Muramatsu, T. (O-arai Engineering Center (Japan))

Recent activities related to thermo-mechanical fatigue, creep and fracture mechanics in Korea nuclear fields
Lee, H.-Y.; Kim, J.-B.; Yoo, B. (Korea Atomic Energy Research Institute (Korea, Republic of)); Park, Y.Y.-W. (Korea Institute of Nuclear Safety (Korea, Republic of))

Tee-junction of LMFR secondary circuit involving thermal, thermomechanical and fracture mechanics assessment on a striping phenomenon
Lee, H.-Y.; Kim, J.-B.; Yoo, B. (Korea Atomic Energy Research Institute (Korea, Republic of))

Results of the thermomechanical and fracture mechanical analysis of pipeline tee-junction break under conditions of interaction between hot sodium jet and main cold sodium flow
Birbryer, P.N.; Kiryushin, A.I.; Zhukov, V.V.; Sobolev, V.A.; Soloviev, S.A. (OKB Mechanical Engineering, Nizhny Novgorod (Russian Federation))

Computational investigation of thermohydraulic aspects of two convergent flows at different temperatures mixed in the tee junction area
Scherbakov, S.I. (Institute of Physics and Power Engineering, Obninsk (Russian Federation))

Benchmark on tee junction: Fatigue damage analysis
Lewis, M.W.J. (AEA Technology pls (United Kingdom))

Thermal striping benchmark exercise: Thermal hydraulic analysis of the Phenix fast reactor secondary pipework T-junction
Stainsby, R.; Martin, D. (AEA Technology plc, Risley, Warrington, Cheshire (United Kingdom))