Tests on the primary-coolant system components for a fast reactor
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
The component tests for the primary cooling system of a fast reactor have been performed on elbows, tees, nozzles and reducers of stainless steel SUS 304. The purposes are to study the adequacy of ASME Boiler and Pressure Vessel Code Section III in low cycle fatigue, to reveal structural safety in fatigue cracking, and to obtain data for the in-service inspection of the fast reactor. Summarizing the results : (1) Stress concentration factor showed the property of secondary stress index. (2) The deflection coefficient given by the design code agreed with that by experiment. (3) Cracks resulting in penetration arose at the places of bending stress. (4) The fatigue life of piping components is lower than that of the material itself. (Mori, K.)
Additional details
Publishing Information
- Journal Title
- Doryokuro Giho
- Journal Issue
- no.15
- Series
- Doryokuro Giho.
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 7273703
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACKS; DEFORMATION; DISTRIBUTION; FATIGUE; FBR TYPE REACTORS; MATERIALS TESTING; PRIMARY COOLANT CIRCUITS; STAINLESS STEEL-304; STRESS ANALYSIS; STRESSES
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; FAST REACTORS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; NICKEL ALLOYS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEELS; TESTING; TRANSITION ELEMENT ALLOYS