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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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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Book Description


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: C. L. Mohr
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 176

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LOCA Simulation in NRU Program

LOCA Simulation in NRU Program PDF Author:
Publisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages :

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LOCA Simulation in NRU Program

LOCA Simulation in NRU Program PDF Author: R. K. Marshall
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 40

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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.

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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Design Basis Neutronics Calculations for NRU-LOCA Experiments

Design Basis Neutronics Calculations for NRU-LOCA Experiments PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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The report describes the neutronics analysis for the LOCA simulation experiments in the NRU reactor. The experimental program will provide greater understanding of nuclear fuel assembly behavior during the heatup, reflood and quench sequence of a hypothetical LOCA. The decay heat and stored heat, which are the energy source in a LOCA will be simulated by fission heat provided by the NRU reactor. The reactor, the test and test operation are described.

Monthly Catalog of United States Government Publications

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

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Monthly Catalogue, United States Public Documents

Monthly Catalogue, United States Public Documents PDF Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1160

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