Experiment Operations Plan for a Loss-of-coolant Accident Simulation in the National Research Universal Reactor PDF Download
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Author: G. E. Russcher
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 136
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Book Description
Author: G. E. Russcher
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 136
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects of LOCA conditions on pressurized water reactor test fuel bundles. This experiment operation plan for the second and third experiments of the program will provide peak fuel cladding temperatures of up to 1172K (1650°F) and 1061K (1450°) respectively. for a long enough time to cause test fuel cladding deformation and rupture in both. Reflood coolant delay times and the reflooding rates for the experiments were selected from thermal-hydraulic data measured in the National Research Universal (NRU) reactor facilities and test train assembly during the first experiment.
Author: C. L. Mohr
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 240
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Author: G. E. Russcher
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 52
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Author: G. E. Russcher
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: G. E. Russcher
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 60
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Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 52
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Author: G. E. Russcher
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52
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Author:
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Category :
Languages : en
Pages :
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Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a series of experiments in the U-2 loop of the National Research Universal Reactor at Chalk River, Ontario, Canada. The first of these experiments includes up to 45 parametric thermal-hydraulic tests to establish the relationship among the reflood delay time of emergency coolant, the reflooding rate, and the resultant fuel rod cladding peak temperature. Subsequent experiments establish the fuel rod failure characteristics at selected peak cladding temperatures. Fuel rod cladding pressurization simulates high burnup fission gas pressure levels of modern PWRs. This document contains both an experiment overview of the LOCA simulation program and a review of the safety analyses performed by Pacific Northwest Laboratory (PNL) to define the expected operating conditions as well as to evaluate the worst case operating conditions. The primary intent of this document is to supply safety information required by the Chalk River Nuclear Laboratories (CRNL), to establish readiness to proceed from one test phase to the next and to establish the overall safety of the experiment. A hazards review summarizes safety issues, normal operation and three worst case accidents that have been addressed during the development of the experiment plan.
Author: G. E. Russcher
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52
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