Calculation of Local Stress and Fatigue Resistance due to Thermal Stratification on Pressurized Surge Line Pipe
Creators
- 1. Center for Nuclear Industry Materials- National Nuclear Energy Agency, Serpong (Indonesia)
- 2. Center for Nuclear Engineering Development-BATAN, Serpong (Indonesia)
Description
Thermal stratification introduces thermal shock effect which results in local stress and fatigue problems that must be considered in the design of nuclear power plant components. Local stress and fatigue calculation were performed on the Pressurize Surge Line piping system of the Pressurize Water Reactor of the Nuclear Power Plant. Analysis was done on the operating temperature between 177 to 343 deg. C and the operating pressure of 16 MPa (160 Bar). The stagnant and transient condition with two kinds of stratification model has been evaluated by the two dimensional finite elements method using the ANSYS program. Evaluation of fatigue resistance is developed based on the maximum local stress using the ASME standard Code formula. Maximum stress of 427 MPa occurred at the upper side of the top half of hot fluid pipe stratification model in the transient case condition. The evaluation of the fatigue resistance is performed on 500 operating cycles in the life time of 40 years and giving the usage value of 0,64 which met to the design requirement for class 1 of nuclear component. The out surge transient were the most significant case in the localized effects due to thermal stratification.
Additional details
Publishing Information
- Journal Title
- AIP Conference Proceedings
- Journal Volume
- 1244
- Journal Issue
- 1
- Journal Page Range
- p. 232-238
- ISSN
- 0094-243X
- CODEN
- APCPCS
Conference
- Title
- 2. international conference on advances in nuclear science and engineering 2009
- Acronym
- ICANSE 2009
- Dates
- 3-4 Nov 2009
- Place
- Bandung (Indonesia)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42003649
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DESIGN; EVALUATION; FATIGUE; FINITE ELEMENT METHOD; FLUIDS; NUCLEAR POWER PLANTS; PRESSURE RANGE MEGA PA; PWR TYPE REACTORS; STRATIFICATION; STRESSES; SURGES; THERMAL SHOCK; TRANSIENTS; TWO-DIMENSIONAL CALCULATIONS; WATER
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL SOLUTION; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; PRESSURE RANGE; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- (c) 2010 American Institute of Physics