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Fuel Assembly Homogenization and Reaction Rate Conservation
Published in Robert E. Masterson, Introduction to Nuclear Reactor Physics, 2017
Although this table is not intended to be an all-inclusive list, it lists some of the most popular computer programs that are available to solve the diffusion equation today. Moreover, some industrial-strength codes like SIMULATE, CITATION, and DIFF-3D are available in many different versions, and these versions can run on many different computers—from IBM mainframes to laptops or even desktops. Many of these programs can be obtained from the Nuclear Energy Agency (NEA) in Paris, France, or from the Radiation Safety Information Computational Center (or RSICC) in Oak Ridge, Tennessee. The URLs for these two important code repositories arewww.oecd-nea.orghttp://www-rsicc.ornl.gov/Finally, SIMULATE, CITATION, and DIFF-3D have been extensively benchmarked against experimental data, and they provide almost all of the features that any nuclear engineer could desire. In the United States, several nuclear utilities have used SIMULATE for their burnup and depletion calculations, and there is an extensive database of operational data to support its use. Most of the time, these programs are designed to solve the diffusion equation with at least two energy groups. However, reactor vendors typically employ between 4 and 10 energy groups, and as a result of this enhanced group structure, their accuracy is very good when they are applied to a specific design. Sometimes another computer program called PDQ-7 (which was originally developed for PWRs at the Bettis Atomic Power Laboratory in the 1970s), is used to perform fine mesh calculations, and its results are then spatially homogenized and fed into the SIMULATE program to perform burnup and depletion calculations. The general process for how this is accomplished is described in the sections that follow.
Features of Particle and Heavy Ion Transport code System (PHITS) version 3.02
Published in Journal of Nuclear Science and Technology, 2018
Tatsuhiko Sato, Yosuke Iwamoto, Shintaro Hashimoto, Tatsuhiko Ogawa, Takuya Furuta, Shin-ichiro Abe, Takeshi Kai, Pi-En Tsai, Norihiro Matsuda, Hiroshi Iwase, Nobuhiro Shigyo, Lembit Sihver, Koji Niita
Monte Carlo particle transport simulation codes are an essential tool used in various fields of research such as radiation shielding, radiological protection, and medical physics. We are therefore developing Particle and Heavy Ion Transport code System (PHITS) [1], which can transport most of the particle species with energies up to 1 TeV (per nucleon for ion) by using several nuclear reaction models and data libraries. The validation and verification of the code were thoroughly performed for various applications on the basis of a benchmark study of more than 50 irradiation scenarios [2]. All contents of the system, such as the source code and executable files, data libraries, and graphic utility, are fully integrated into one package and have been distributed to many countries via the Research organization for Information Science and Technology (RIST), Data Bank of the Organization for Economic Co-operation and Development's Nuclear Energy Agency (OECD/NEA DB), and Radiation Safety Information Computational Center (RSICC).