Application of MCNP for neutronic calculations at VR-1 training reactor

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F14%3A00317483" target="_blank" >RIV/68407700:21340/14:00317483 - isvavai.cz</a>

Result on the web

<a href="https://sna-and-mc-2013-proceedings.edpsciences.org/articles/snamc/abs/2014/01/snamc2013_05103/snamc2013_05103.html" target="_blank" >https://sna-and-mc-2013-proceedings.edpsciences.org/articles/snamc/abs/2014/01/snamc2013_05103/snamc2013_05103.html</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1051/snamc/201405103" target="_blank" >10.1051/snamc/201405103</a>

Result language

angličtina

Original language name

Application of MCNP for neutronic calculations at VR-1 training reactor

Original language description

The paper presents utilization of Monte Carlo MCNP transport code for neutronic calculations of training reactor VR-1. Results of calculations are compared with results of measurements realized during last few critical experiments with various reactor core configurations. Very good agreement between calculations and measurements is observed.

Czech name

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Czech description

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Type

O - Miscellaneous

CEP classification

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OECD FORD branch

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Project

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Continuities

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Publication year

2014

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů