Burst criterion for Indian PHWR fuel cladding under simulated loss-of-coolant accident
The indigenous nuclear power program of India is based mainly on a series of Pressurised Heavy Water Reactors (PHWRs). A burst correlation for Indian PHWR fuel claddings has been developed and empirical burst parameters are determined. The burst correlation is developed from data available in litera...
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| Format: | Article |
| Language: | English |
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Elsevier
2019-09-01
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| Series: | Nuclear Engineering and Technology |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573319300166 |