Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accident

Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accident PDF Author: C. L. Mohr
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 338

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Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accident

Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accident PDF Author: C. L. Mohr
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 338

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Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accidents

Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accidents PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accident

Prototypic Thermal-hydraulic Experiment in NRU to Simulate Loss-of-coolant Accident PDF Author: C. L. Mohr
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 332

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LOCA Simulation in the National Research Universal Reactor Program

LOCA Simulation in the National Research Universal Reactor Program PDF Author: C. L. Mohr
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 240

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LOCA Simulation in NRU Program

LOCA Simulation in NRU Program PDF Author: Cecil Leeburn Wilson
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 240

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NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 336

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LOCA Simulation in the NRU Reactor

LOCA Simulation in the NRU Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized water reactor fuel rods. This second experiment of the program produced peak fuel cladding temperatures of 1148K (1607°F) and resulted in six ruptured fuel rods. Test data and initial results from the experiment are presented here in the form of photographs and graphical summaries. These results are also compared with the preceding prototypic thermal-hydraulic test results and with computer model test predictions.

Experiment Operations Plan for a Loss-of-coolant Accident Simulation in the National Research Universal Reactor

Experiment Operations Plan for a Loss-of-coolant Accident Simulation in the National Research Universal Reactor PDF Author: G. E. Russcher
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52

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Reactor Safety Research Programs

Reactor Safety Research Programs PDF Author: S. K. Edler
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 76

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Monthly Catalog of United States Government Publications

Monthly Catalog of United States Government Publications PDF Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1072

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