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- W1572167265 abstract "In the past, criticality safety analyses related to the handling and storage of fissile materials were obtained from critical experiments, nuclear safety guides, and handbooks. As a result of rising costs and time delays associated with critical experiments, most experimental facilities have been closed, triggering an increased reliance on computational methods. With this reliance comes the need and requirement for redundant validation by independent criticality codes. Currently, the KENO Monte Carlo transport code is the most widely used tool for criticality safety calculations. For other transport codes, such as MCNP, to be accepted by the criticality safety community as a redundant validation tool they must be able to reproduce experimental results at least as well as KENO. The Monte Carlo neutron, photon, and electron transport code MCNP, has an extensive list of attractive features, including continuous energy cross sections, generalized 3-D geometry, time dependent transport, criticality k{sub eff} calculations, and comprehensive source and tally capabilities. It is widely used for nuclear criticality analysis, nuclear reactor shielding, oil well logging, and medical dosimetry calculations. This report specifically addresses criticality and benchmarks the KENO 25 problem test set. These sample problems constitute the KENO standard benchmark set and represent a relatively widemore » variety of criticality problems. The KENO Monte Carlo code was chosen because of its extensive benchmarking against analytical and experimental criticality results. Whereas the uncertainty in experimental parameters generally prohibits code validation to better than about 1% in k{sub eff}, the value of k{sub eff} for criticality is considered unacceptable if it deviates more than a few percent from measurements.« less" @default.
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- W1572167265 date "1993-04-01" @default.
- W1572167265 modified "2023-09-26" @default.
- W1572167265 title "MCNP/KENO criticality benchmarks" @default.
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