توضیحاتی در مورد کتاب Validation of fast reactor thermomechanical and thermohydraulic codes : final report of a co-ordinated research project 1996-1999
نام کتاب : Validation of fast reactor thermomechanical and thermohydraulic codes : final report of a co-ordinated research project 1996-1999
عنوان ترجمه شده به فارسی : اعتبار سنجی کدهای ترمومکانیکی و ترموهیدرولیک راکتور سریع: گزارش نهایی یک پروژه تحقیقاتی هماهنگ 1996-1999
سری : IAEA-TECDOC, 1318
نویسندگان : A Rineiskii, A Stanculescu, International Atomic Energy Agency., Harmonization and Validation of Fast Reactor Thermomechanical and Thermo- Hydraulic Codes and Relations using Experimental Data
ناشر : International Atomic Energy Agency
سال نشر : 2002
تعداد صفحات : 262
ISBN (شابک) : 9201099037 , 9789201099037
زبان کتاب : English
فرمت کتاب : pdf
حجم کتاب : 4 مگابایت
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فهرست مطالب :
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