Availability of a pressurized water reactor pressure vessel after a small LOCA
Description
The integrity of a pressure vessel after a loss-of-coolant accident is investigated. The pressure and temperature in the pressure vessel is found by RELAP-4 for different break sizes. The effect of the pressure and thermal shock on the pressure vessel is evaluated by a two-dimensional finite element method (code SAP). By assuming axisymmetry, stress resulting from the shocks is calculated in the nozzle shell and in the beltline region of the pressure vessel. Similar calculations are carried out for the closure head and the lower head regions of the pressure vessel. Fracture mechanics is used to evaluate the stress intensity factor as a function of crack depth, and the critical crack depths are then obtained at various locations in the pressure vessel. The post-LOCA usability of the pressure vessel is predicted by comparing the stress intensity factor with the fracture toughness of the steel. (Auth.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 52
- Journal Issue
- 1
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 59-66
- ISSN
- 0029-5493
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 10461211
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACKS; FINITE ELEMENT METHOD; FRACTURE PROPERTIES; FRACTURES; HIGH TEMPERATURE; LOSS OF COOLANT; PRESSURE GRADIENTS; PRESSURE VESSELS; R CODES; SPATIAL DISTRIBUTION; STEEL-ASTM-A533-B; STRESS INTENSITY FACTORS; STRESSES; THERMAL SHOCK; TWO-DIMENSIONAL CALCULATIONS; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; CARBON STEELS; COMPUTER CODES; CONTAINERS; DISTRIBUTION; ENRICHED URANIUM REACTORS; FAILURES; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS