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L.O.C.A. simulation in N.R.U. program

Title:L.O.C.A. simulation in N.R.U. program
Alternate title:LOCA simulation in NRU program : the continuous measurement of coolant liquid level during the MT-4 experiment in the NRU reactor
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Note:Washington, D. C. : U.S. Nuclear Regulatory Commission, 1983., 1983
  
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Subject:Light water reactors -- Accidents -- Ontario -- Simulation methods
Subject:Ontario
Subject:Pressurized water reactors -- Loss of coolant -- Simulation methods
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