Characterization of the graphite pile as a source of thermal
neutrons

J 2015

Characterization of the graphite pile as a source of thermal neutrons

VYKYDAL, Zdeněk; Miloslav KRÁLÍK; Aleš JANČÁŘ; Zdeněk KOPECKÝ; Jan DRESSLER et al.

Základní údaje

Originální název

Characterization of the graphite pile as a source of thermal neutrons

Název česky

Charakteristika grafitového zdroje termálních neutronů

Autoři

VYKYDAL, Zdeněk; Miloslav KRÁLÍK; Aleš JANČÁŘ; Zdeněk KOPECKÝ; Jan DRESSLER a Martin VEŠKRNA

Vydání

Radiation Physics and Chemistry, Elsevier, 2015, 0969-806X

Další údaje

Jazyk

angličtina

Typ výsledku

Článek v odborném periodiku

Obor

10304 Nuclear physics

Stát vydavatele

Spojené státy

Utajení

není předmětem státního či obchodního tajemství

Odkazy

URL

Impakt faktor

Impact factor: 1.207

Označené pro přenos do RIV

Ano

Kód RIV

RIV/00216224:14330/15:00083306

Organizační jednotka

Fakulta informatiky

Klíčová slova česky

Termální neutrony; proporcionální detektor He-3; grafit

Klíčová slova anglicky

Thermal neutrons; Graphite pile; Cadmium ratio; 3He proportional detectors

Příznaky

Mezinárodní význam, Recenzováno

Změněno: 2. 5. 2016 06:21, RNDr. Pavel Šmerk, Ph.D.

Anotace

V originále

A new graphite pile designed to serve as a standard source of thermal neutrons has been built at the Czech Metrology Institute. Actual dimensions of the pile are 1.95 m (W)×1.95 m (L)×2.0 m (H). At its center, there is a measurement channel whose dimensions are 0.4 m×0.4 m×1.25 m (depth). The channel is equipped with a calibration bench, which allows reproducible placement of the tested/calibrated device. At a distance of 80 cm from the channel axis, six holes are symmetrically located allowing the placement of radionuclide neutron sources of Pu–Be and/or Am–Be type. Spatial distribution of thermal neutron fluence in the cavity was calculated in detail with the MCNP neutron transport code. Experimentally, it was measured with two active detectors: a small 3He proportional detector by the French company LMT, type 0.5 NH 1/1 KF, and a silicon pixel detector Timepix with 10B converter foil. The relative values of thermal neutron fluence rate obtained with active detectors were converted to absolute ones using thermal neutron fluence rates measured by means of gold foil activation. The quality of thermal neutron field was characterized by the cadmium ratio.

Citovat

VYKYDAL, Zdeněk; Miloslav KRÁLÍK; Aleš JANČÁŘ; Zdeněk KOPECKÝ; Jan DRESSLER a Martin VEŠKRNA. Characterization of the graphite pile as a source of thermal neutrons. Radiation Physics and Chemistry. Elsevier, 2015, roč. 116, November 2015, s. 65-68. ISSN 0969-806X. Dostupné z: https://doi.org/10.1016/j.radphyschem.2015.01.028.

@article{1305265,
   author = {Vykydal, Zdeněk and Králík, Miloslav and Jančář, Aleš and Kopecký, Zdeněk and Dressler, Jan and Veškrna, Martin},
   article_number = {November 2015},
   doi = {https://doi.org/10.1016/j.radphyschem.2015.01.028},
   keywords = {Thermal neutrons; Graphite pile; Cadmium ratio; 3He proportional detectors},
   language = {eng},
   issn = {0969-806X},
   journal = {Radiation Physics and Chemistry},
   title = {Characterization of the graphite pile as a source of thermal neutrons},
   url = {http://www.sciencedirect.com/science/article/pii/S0969806X15000353},
   volume = {116},
   year = {2015}
}

TY  - JOUR
ID  - 1305265
AU  - Vykydal, Zdeněk - Králík, Miloslav - Jančář, Aleš - Kopecký, Zdeněk - Dressler, Jan - Veškrna, Martin
PY  - 2015
TI  - Characterization of the graphite pile as a source of thermal neutrons
JF  - Radiation Physics and Chemistry
VL  - 116
IS  - November 2015
SP  - 65-68
EP  - 65-68
PB  - Elsevier
SN  - 0969806X
KW  - Thermal neutrons
KW  - Graphite pile
KW  - Cadmium ratio
KW  - 3He proportional detectors
UR  - http://www.sciencedirect.com/science/article/pii/S0969806X15000353
N2  - A new graphite pile designed to serve as a standard source of thermal neutrons has been built at the Czech Metrology Institute. Actual dimensions of the pile are 1.95 m (W)×1.95 m (L)×2.0 m (H). At its center, there is a measurement channel whose dimensions are 0.4 m×0.4 m×1.25 m (depth). The channel is equipped with a calibration bench, which allows reproducible placement of the tested/calibrated device. At a distance of 80 cm from the channel axis, six holes are symmetrically located allowing the placement of radionuclide neutron sources of Pu–Be and/or Am–Be type. Spatial distribution of thermal neutron fluence in the cavity was calculated in detail with the MCNP neutron transport code. Experimentally, it was measured with two active detectors: a small 3He proportional detector by the French company LMT, type 0.5 NH 1/1 KF, and a silicon pixel detector Timepix with 10B converter foil. The relative values of thermal neutron fluence rate obtained with active detectors were converted to absolute ones using thermal neutron fluence rates measured by means of gold foil activation. The quality of thermal neutron field was characterized by the cadmium ratio.
ER  -

VYKYDAL, Zdeněk; Miloslav KRÁLÍK; Aleš JANČÁŘ; Zdeněk KOPECKÝ; Jan DRESSLER a Martin VEŠKRNA. Characterization of the graphite pile as a source of thermal neutrons. \textit{Radiation Physics and Chemistry}. Elsevier, 2015, roč.~116, November 2015, s.~65-68. ISSN~0969-806X. Dostupné z: https://doi.org/10.1016/j.radphyschem.2015.01.028.

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