Suggested Topics within your search.
Suggested Topics within your search.
- Nuclear reactor accidents
- Nuclear power plants 108
- Accidents 88
- Safety measures 87
- Nuclear reactors 53
- Computer simulation 43
- Pressurized water reactors 28
- Computer programs 17
- Loss of coolant 16
- Emergency management 15
- Research 14
- Risk assessment 13
- Nuclear facilities 12
- Prevention 12
- Evaluation 11
- Fukushima Nuclear Disaster, Japan, 2011 11
- Water cooled reactors 11
- Analysis 10
- Boiling water reactors 9
- Data processing 9
- Environmental aspects 9
- Radiation 9
- Testing 9
- Containment 8
- Health aspects 8
- International cooperation 8
- Radioactive pollution 8
- Chernobyl Nuclear Accident, Chornobylʹ, Ukraine, 1986 7
- Management 7
- Decommissioning 6
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1
Modification of USNRC's FRAP-T6 fuel rod transient code for high burnup VVER fuel
Published 1999Government Document Microfilm Book -
2
Modification of IPSN's SCANAIR fuel rod transient code for high burnup VVER fuel
Published 1999Government Document Microfilm Book -
3
Contrast of RELAP5/MOD3.2 results from different computing platforms /
Published 1999Online Access
Online Access
Government Document eBook -
4
Analysis of semiscale test S-LH-2 using RELAP5/MOD2 /
Published 1992Online Access
Online Access
Government Document eBook -
5
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7
Result of BETHSY test 9.1.b using RELAP5/MOD3 /
Published 1998Online Access
Government Document eBook -
8
RELAP5 assessment against PACTEL experimental data /
Published 1998Online Access
Government Document eBook -
9
RELAP5/MOD3 subcooled boiling model assessment /
Published 1998Online Access
Online Access
Government Document eBook -
10
Recirculation suction large break LOCA analysis of the Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1) /
Published 1992Online Access
Online Access
Government Document eBook -
11
Assessment of the turbine trip transient in cofrentes NPP with TRAC-BF1 /
Published 1993Online Access
Government Document eBook -
12
Assessment of MSIV full closure for Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1) /
Published 1993Online Access
Government Document eBook -
13
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14
WASH-1400, the reactor safety study : the introduction of risk assessment to the regulation of nuclear reactors.
Published 2016Online Access
Online Access
Government Document eBook -
15
BWR ECCS pump suction concerns following a LOCA /
Published 2016Online Access
Online Access
Government Document eBook -
16
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18
Nowadays tools for graphical post-processing of TRAC-BF1 results
Published 2000Government Document Microfilm Book -
19
Development of a pressure drop calculation method for debris-covered sump screens in support of generic safety issue 191 /
Published 2007Online Access
Online Access
Government Document eBook -
20