Search results
Results from the WOW.Com Content Network
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
Scram: A Nuclear Power Plant Simulation is an educational simulation video game developed for Atari 8-bit computers by Chris Crawford and published by Atari, Inc. in 1981. [1] Written in Atari BASIC, Scram uses differential equations to simulate nuclear reactor behavior. The player controls the valves and switches of the reactor directly with ...
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.
Technical data on RBMK-1500 reactor at Ignalina nuclear power plant – a decommissioned RBMK reactor. Chernobyl – A Canadian Perspective – A brochure describing nuclear reactors in general and the RBMK design in particular, focusing on the safety differences between them and CANDU reactors. Published by Atomic Energy of Canada Limited.
Not all of the heat in a nuclear reactor is generated by the chain reaction that a scram is designed to stop. For a reactor that is scrammed after holding a constant power level for an extended period (greater than 100 hrs), about 7% of the steady-state power will remain after initial shutdown due to fission product decay that cannot be stopped.
A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction. They are used for commercial electricity, marine propulsion, weapons production and research. Fissile nuclei (primarily uranium-235) absorb single neutrons and split, releasing energy and multiple neutrons, which can induce further fission.
In the context of nuclear reactors, a safety code is a computer program used to analyze the safety of a reactor, or to simulate possible accident conditions. This article appears to be a dictionary definition .
Specific areas of application include, but are not limited to, radiation protection and dosimetry, radiation shielding, radiography, medical physics, nuclear criticality safety, detector design and analysis, nuclear oil well logging, accelerator target design, fission and fusion reactor design, decontamination and decommissioning. The code ...