Benchmark experiments for validation of reaction rates determination in reactor dosimetry

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F14%3A00213681" target="_blank" >RIV/68407700:21340/14:00213681 - isvavai.cz</a>
Result on the web
<a href="http://dx.doi.org/10.1016/j.radphyschem.2014.02.004" target="_blank" >http://dx.doi.org/10.1016/j.radphyschem.2014.02.004</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.radphyschem.2014.02.004" target="_blank" >10.1016/j.radphyschem.2014.02.004</a>

Result language
angličtina
Original language name
Benchmark experiments for validation of reaction rates determination in reactor dosimetry
Original language description
The precision of Monte Carlo calculations of quantities of neutron dosimetry strongly depends on precision of reaction rates prediction. Research reactor represents a very useful tool for validation of the ability of a code to calculate such quantities as it can provide environments with various types of neutron energy spectra. Especially, a zero power research reactor with well-defined core geometry and neutronic properties enables precise comparison between experimental and calculated data. Thus, at the VR-1 zero power research reactor, a set of benchmark experiments were proposed and carried out to verify the MCNP Monte Carlo code ability to predict correctly the reaction rates. For that purpose two frequently used reactions were chosen: He-3(n,p)H-3 and Au-197(n,?)Au-198. The benchmark consists of response measurement of small He-3 gas filled detector in various positions of reactor core and of activated gold wires placed inside the core or to its vicinity. The reaction rates were
Czech name
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Czech description
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Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
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Project
<a href="/en/project/TA01020352" target="_blank" >TA01020352: Increasing utilization of nuclear fuel through optimization of an inner fuel cycle and calculation of neutron-physics characteristics of nuclear reactor cores</a><br>
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year
2014
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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