Characterization of the Graphite Moderated Thermal Neutron Field at CMI

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00177016%3A_____%2F17%3AN0000054" target="_blank" >RIV/00177016:_____/17:N0000054 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1093/rpd/ncx190" target="_blank" >https://doi.org/10.1093/rpd/ncx190</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1093/rpd/ncx190" target="_blank" >10.1093/rpd/ncx190</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Characterization of the Graphite Moderated Thermal Neutron Field at CMI

Popis výsledku v původním jazyce

The graphite pile was set up at CMI to provide reference thermal neutron field for metrology and dosimetry purposes. It consists of three Pu–Be and three Am–Be radionuclide sources located in a 1.95 m (width) × 1.95 m (length) × 2.0m (height) graphite moderator block. The neutron field in the volume of the experimental channel with dimensions of 40 cm × 40 cm × 135 cm (depth) was characterised experimentally and by Monte-Carlo calculations. Neutron fluence was determined by the activation of gold foils and Manganese tablets irradiated in nine different positions and by two 3He detectors of different construction irradiated in one position (bare and covered in three spherical PE moderators of 3, 3.5 and 4 inch diameter). Weighted mean value of the neutron fluence rate measured by all the abovementioned detectors in the pile centre was used as a calibration factor for the Monte-Carlo model predictions. The neutron spectral fluence rate calculated by validated Monte-Carlo model was used to determine the conventionally true ambient and personal dose equivalent rates at different positions.

Název v anglickém jazyce

Characterization of the Graphite Moderated Thermal Neutron Field at CMI

Popis výsledku anglicky

The graphite pile was set up at CMI to provide reference thermal neutron field for metrology and dosimetry purposes. It consists of three Pu–Be and three Am–Be radionuclide sources located in a 1.95 m (width) × 1.95 m (length) × 2.0m (height) graphite moderator block. The neutron field in the volume of the experimental channel with dimensions of 40 cm × 40 cm × 135 cm (depth) was characterised experimentally and by Monte-Carlo calculations. Neutron fluence was determined by the activation of gold foils and Manganese tablets irradiated in nine different positions and by two 3He detectors of different construction irradiated in one position (bare and covered in three spherical PE moderators of 3, 3.5 and 4 inch diameter). Weighted mean value of the neutron fluence rate measured by all the abovementioned detectors in the pile centre was used as a calibration factor for the Monte-Carlo model predictions. The neutron spectral fluence rate calculated by validated Monte-Carlo model was used to determine the conventionally true ambient and personal dose equivalent rates at different positions.

Druh

J_ost - Ostatní články v recenzovaných periodicích

CEP obor

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OECD FORD obor

10304 - Nuclear physics

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2017

Kód důvěrnosti údajů

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

Název periodika

Radiation Protection Dosimetry

ISSN

0144-8420

e-ISSN

1742-3406

Svazek periodika

"neuveden"

Číslo periodika v rámci svazku

September 2017

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

3

Strana od-do

"nestrankovano"

Kód UT WoS článku

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EID výsledku v databázi Scopus

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