Validation of fast reactor thermomechanical and thermohydraulic codes : final report of a co-ordinated research project 1996-1999

COVER......Page 1 FOREWORD......Page 3 EDITORIAL NOTE......Page 4 CONTENTS......Page 5 1. TECHNICAL BACKGROUND FOR THE CO-ORDINATED RESEARCH PROJECT......Page 7 2.1. Presentation of the problem......Page 8 2.2. Data provided......Page 9 2.3. Thermalhydraulic and thermal results required for comparison with experience......Page 10 3. EXPERIMENTAL ACTIVITIES ON THERMOMECHANICS AND FRACTURE MECHANICS AT THE PARTICIPATING INSTITUTES......Page 11 4. SUMMARY OF ACTIVITIES WITHIN THE CRP ON THERMOHYDRAULICS, THERMOMECHANICS AND FRACTURE MECHANICS: RESULTS FROM INDIVIDUAL PROJECTS......Page 14 6.1. The main results......Page 18 6.2. Recommendations......Page 19 1. THERMOHYDRAULIC METHODS......Page 22 2. FATIGUE DAMAGE ANALYSIS......Page 28 3. CRACK PROPAGATION ANALYSIS......Page 33 Annex WORK PERFORMED BY THE RESEARCH GROUPS AT THE PARTICIPATING INSTITUTES WITHIN THE CRP......Page 35 THERMOMECHANICAL AND THERMOHYDRAULIC ANALYSES OF A T-JUNCTION USING EXPERIMENTAL DATA......Page 37 THERMAL HYDRAULICS AND THERMOMECHANICAL ANALYSIS OF THERMAL STRIPING IN A MIXING TEE-JUNCTION OF SECONDARY SODIUM CIRCUIT OF PHÉNIX REACTOR......Page 69 THERMOMECHANICAL AND FRACTURE MECHANICS ANALYSIS ON A TEE JUNCTION OF LMFR SECONDARY CIRCUIT DUE TO THERMAL STRIPING PHENOMENA......Page 95 THERMOHYDRAULICS COMPUTER CODE SYSTEM AND COMPUTATIONAL RESULTS ON THERMAL STRIPING PHENOMENA AT A TEE JUNCTION OF LMFR SECONDARY CIRCUIT WITH THE SYSTEM......Page 123 RECENT ACTIVITIES RELATED TO THERMO-MECHANICAL FATIGUE, CREEP AND FRACTURE MECHANICS IN KOREA NUCLEAR FIELDS......Page 151 TEE-JUNCTION OF LMFR SECONDARY CIRCUIT INVOLVING THERMAL, THERMOMECHANICAL AND FRACTURE MECHANICS ASSESSMENT ON A STRIPING PHENOMENON......Page 159 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......Page 174 COMPUTATIONAL INVESTIGATION OF TERMOHYDRAULIC ASPECTS OF TWO CONVERGENT FLOWS AT DIFFERENT TEMPERATURES MIXED IN THE TEE JUNCTION AREA......Page 192 THERMAL STRIPING BENCHMARK EXERCISE: THERMAL HYDRAULIC ANALYSIS OF THE PHENIX FAST REACTOR SECONDARY PIPEWORK T-JUNCTION......Page 212 BENCHMARK ON TEE JUNCTION: FATIGUE DAMAGE ANALYSIS......Page 233 LIST OF PARTICIPANTS......Page 261 This publication, arising from a Co-ordinated Research Project (CRP), describes the main results and recommendations. 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 is also included.