Thermal-hydraulic analysis of nuclear reactors /
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TextDescription: pages cmDDC classification: 621.4831
| Item type | Current location | Home library | Call number | Status | Date due | Barcode | Item holds |
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US-Pakistan Center for Advanced Studies in Energy (USPCAS-E) | US-Pakistan Center for Advanced Studies in Energy (USPCAS-E) | 621.4831 ZOH-T (Browse shelf) | Available | cas-e0001961 |
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| 621.4831 STA-N 2007 Nuclear reactor physics / | 621.4831 WAK-N 1993 Nuclear heat transport | 621.4831 ZOH-T Thermal-hydraulic analysis of nuclear reactors / | 621.4831 ZOH-T Thermal-hydraulic analysis of nuclear reactors / | 621.4832 MCC-R 1981 Reliability and risk analysis : | 621.4832 MCC-R 1981 Reliability and risk analysis : | 621.4833 HOF Materials for nuclear plants : from safe design to residual life assessments |
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