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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]
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 ...
Upon completion of each puzzle, the player's performance is compared on a leaderboard based on the number of instructions placed in their reactors, the number of cycles it took to meet the quota, and the number of reactors required to meet the solution. [1] The player also has an option to upload videos of their solution to YouTube.
An expansion of the plant begun in 2006 added four new Korean-sourced reactors, the so-called Shin Kori reactors (Korean: 신고리; shin 신 meaning "new"). The first pair of Shin Kori reactors are of the OPR-1000 design, while the second two are the APR-1400 design. Shin Kori 1 and 2 achieved commercial operations in 2011 and 2012 ...
The reactor was unveiled by Babcock & Wilcox in June 2009. [3] [4] In July 2010, Babcock & Wilcox announced a formal alliance with Bechtel called Generation mPower LLC. [5]At the same time, Babcock & Wilcox announced that it would build a test facility for the mPower reactor design at the Center for Advanced Engineering and Research in Bedford County, Virginia. [6]
TRIGA is a swimming pool reactor that can be installed without a containment building, and is designed for research and testing use by scientific institutions and universities for purposes such as undergraduate and graduate education, private commercial research, non-destructive testing and isotope production.
1943 Reactor diagram using boron control rods. Control rods are inserted into the core of a nuclear reactor and adjusted in order to control the rate of the nuclear chain reaction and, thereby, the thermal power output of the reactor, the rate of steam production, and the electrical power output of the power station.
An operational license for the MAPLE I reactor was granted in 1999, and the reactor went critical for the first time in early 2000. MAPLE II followed in the fall of 2003. Problems with the reactors during the testing period, most notably an unexpected positive power co-efficient of reactivity , led to the cancellation of the project in 2008 and ...