Results 21 to 30 of about 167,510,152 (115)
Loss-of-coolant accident analyses of the Advanced Neutron Source Reactor [PDF]
, 1991 Currently in the conceptual design stage, the Advanced Neutron Source Reactor (ANSR) will operate at a high heat flux, a high mass flux, an a high degree of coolant subcooling.
Wendel, M.W. (Martin Marietta Energy Systems, Inc., Oak Ridge, TN (USA)) +2 more
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EXPERIMENT OPERATIONS PLAN FOR A LOSS-OF-COOLANT ACCIDENT SIMULATION IN THE NATIONAL RESEARCH UNIVERSAL REACTOR [PDF]
, 1981 Pressurized water reactor loss-of-coolant accident 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.
Nealley, C. +9 more
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Analysis of mass transfer processes in a reactor during a loss-of-coolant accident
, 2018 The purpose of the work was to optimize the parameters of the spillage system equipped with a gas pressure hydroaccumulator for a ship pressurized water reactor in a loss-of-coolant accident.
Lepyokhin, Andrey +5 more
core +1 more source
Hydrogen Flammability Data and Application to PWR Loss-of-coolant Accident [PDF]
, 1957 Supplemental to WAPD-SC-54l. A summary is presented of generalized data on the flammability of hydrogen in steam-air mixtures. The flammability data are applied to a postulated Pressurized Water Reactor loss-of-coolant accident and to estimates of the ...
Shapiro, Z. M., Moffette, T. R.
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Definition of loss-of-coolant accident radiation source. [PWR; BWR]
, 1978 Meaningful qualification testing of nuclear reactor components requires a knowledge of the radiation fields expected in a loss-of-coolant accident (LOCA). The overall objective of this program is to define the LOCA source terms and compare these with the
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Loss of coolant accident in pressurized water reactor [PDF]
, 2012 Diplomsko delo podaja nekaj splošnih informacij o tlačnovodnih jedrskih reaktorjih in termohidravličnih razmerah v njem. Na demonstracijski napravi START so bili opravljeni štirje eksperimenti simulacije izgube hladilnega medija v hladni veji ...
Holler, Tadej
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Columbia Accident Investigation Board Report: Volume 4. Other Technical Documents
, 2003 Fourth volume of the final report produced by the Columbia Accident Investigation Board including documents produced by NASA and other organizations which were provided to the Columbia Accident Investigation Board in support of its inquiry into the ...
Columbia Accident Investigation Board
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ACCIDENT ANALYSIS FOR ATUCHA II NUCLEAR POWER PLANT [PDF]
, 2007 The intent of this part is to describe the NPP Atucha II with an net electrical power of 692 MW. The plant is equipped with a heavy water pressure vessel reactor of the same type as used in the Atucha I NPP with a net electrical output of 340 MW. The NPP
LAZZERINI, DAVIDE
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Columbia Accident Investigation Board Report: Volume 5. Other Significant Documents
, 2003 Fifth volume of the final report produced by the Columbia Accident Investigation Board including documents produced by NASA and other organizations that were provided to the Columbia Accident Investigation Board in support of its inquiry into the ...
Columbia Accident Investigation Board
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, 2003 Fifth volume of the final report produced by the Columbia Accident Investigation Board including documents produced by NASA and other organizations that were provided to the Columbia Accident Investigation Board in support of its inquiry into the ...
Columbia Accident Investigation Board
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