ASTM E900-21e1 PDF
Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Дата публикации:
- 26 ноября 2025 г.
- SKU:
- ASTM E900-21e1
Abstract
Significance and Use 4.1 Operation of commercial power reactors must conform to pressure-temperature limits during heatup and cooldown to prevent over-pressurization at temperatures that might cause non-ductile behavior in the presence of ...
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