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DRAGON 3.05D, Reactor Cell Calculation System with Burnup nesc0784 DSNP, Program and Data Library System for Dynamic Simulation of Nuclear Power Plant nea-1683 ERANOS 2.3N, Modular code and data system for fast reactor neutronics analyses nea-1916 FINPSA TRAINING 2.2.0.1 -R-, a PSA model in consisting of event trees, fault trees, and cut sets
RELAP5-3D is an outgrowth of the one-dimensional RELAP5/MOD3 code developed at Idaho National Laboratory (INL) for the U.S. Nuclear Regulatory Commission (NRC). The U.S. Department of Energy (DOE) began sponsoring additional RELAP5 development in the early 1980s to meet its own reactor safety assessment needs.
This game's title, "SCRAM", is taken from the term for an emergency shutdown of a nuclear reactor. It refers to immediately inserting all control rods into the reactor core to stop the reaction process. [2] The game also recreates the Three Mile Island Unit 2 nuclear reactor and allowed players to recreate the events that took place there in ...
Time base correction (TBC) is a technique to reduce or eliminate errors caused by mechanical instability present in analog recordings on mechanical media. Without time base correction, a signal from a videotape recorder (VTR) or videocassette recorder (VCR), cannot be mixed with other, more time-stable devices such as character generators and video cameras found in television studios and post ...
A high-temperature gas-cooled reactor (HTGR) is a type of gas-cooled nuclear reactor which uses uranium fuel and graphite moderation to produce very high reactor core output temperatures. [1] All existing HTGR reactors use helium coolant. The reactor core can be either a "prismatic block" (reminiscent of a conventional reactor core) or a ...
Control rods are usually used in control rod assemblies (typically 20 rods for a commercial PWR assembly) and inserted into guide tubes within the fuel elements. Control rods often stand vertically within the core. In PWRs they are inserted from above, with the control rod drive mechanisms mounted on the reactor pressure vessel head. In BWRs ...
The OPR-1000 is a South Korean-designed two-loop 1000 MWe PWR Generation II nuclear reactor, developed by KHNP and KEPCO. [1] The OPR-1000 was originally designated as the Korean Standard Nuclear Power Plant (KSNP), and was re-designated as the OPR-1000 in 2005 for foreign sales. [2]
The X-10 Graphite Reactor is a decommissioned nuclear reactor at Oak Ridge National Laboratory in Oak Ridge, Tennessee. Formerly known as the Clinton Pile and X-10 Pile , it was the world's second artificial nuclear reactor (after Enrico Fermi 's Chicago Pile-1 ) and the first intended for continuous operation.