ASTM STP156320120035 PDF
Development of a Predictive Wear Model for Grid-to-Rod Fretting in Light Water Nuclear Reactors
Название (английский):
ASTM STP156320120035
Development of a Predictive Wear Model for Grid-to-Rod Fretting in Light Water Nuclear Reactors
- Статус документа:
- D
- Формат:
- Электронный (PDF)
- SKU:
- ASTM STP156320120035
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Abstract
The U.S. Dept. of Energy is supporting a multi-party, five-year program called the Consortium for Advanced Simulation of Light Water Reactors (CASL). Its mission is to develop simulations of light water nuclear reactor (LWR) performance tha...
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