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  2. RELAP5-3D - Wikipedia

    en.wikipedia.org/wiki/RELAP5-3D

    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.

  3. Gilbert U-238 Atomic Energy Laboratory - Wikipedia

    en.wikipedia.org/wiki/Gilbert_U-238_Atomic...

    Gilbert cloud chamber, assembled An alternative view of kit contents. The lab contained a cloud chamber allowing the viewer to watch alpha particles traveling at 12,000 miles per second (19,000,000 m/s), a spinthariscope showing the results of radioactive disintegration on a fluorescent screen, and an electroscope measuring the radioactivity of different substances in the set.

  4. List of software for nuclear engineering - Wikipedia

    en.wikipedia.org/wiki/List_of_software_for...

    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

  5. High-temperature gas-cooled reactor - Wikipedia

    en.wikipedia.org/wiki/High-temperature_gas...

    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 ...

  6. Generation IV reactor - Wikipedia

    en.wikipedia.org/wiki/Generation_IV_reactor

    The very-high-temperature reactor (VHTR) uses a graphite-moderated core with a once-through uranium fuel cycle, using helium or molten salt. This reactor design envisions an outlet temperature of 1,000°C. The reactor core can be either a prismatic-block or a pebble bed reactor design.

  7. Integral Molten Salt Reactor - Wikipedia

    en.wikipedia.org/wiki/Integral_Molten_Salt_Reactor

    The integral molten salt reactor (IMSR) is a nuclear power plant design targeted at developing a commercial product for the small modular reactor (SMR) market. It employs molten salt reactor technology which is being developed by the Canadian company Terrestrial Energy .

  8. Nuclear power in Canada - Wikipedia

    en.wikipedia.org/wiki/Nuclear_power_in_Canada

    ZEEP (left), NRX (right) and NRU (back) reactors at Chalk River, 1954. In 1944, approval was given to proceed with the construction of the smaller ZEEP (Zero Energy Experimental Pile) test reactor at Chalk River Nuclear Laboratories in Ontario and on September 5, 1945, at 3:45 p.m., the 10-watt ZEEP achieved the first self-sustained nuclear reaction outside the United States.

  9. Magnox - Wikipedia

    en.wikipedia.org/wiki/Magnox

    The reactor buildings of Bradwell magnox nuclear power station. The magnox reactors were considered at the time to have a considerable degree of inherent safety because of their simple design, low power density, and gas coolant. Because of this they were not provided with secondary containment features. A safety design principle at the time was ...