Experimental determination of the optimum geometry for a thermal-neutron flux standard

1967 ◽  
Vol 23 (4) ◽  
pp. 1098-1100 ◽  
Author(s):  
O. L. Andreev ◽  
I. A. Yaritsyna
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Experimental Determination ◽  
Thermal Neutron Flux ◽  
Optimum Geometry

Experimental determination of the thermal neutron flux around two different types of high intensity 252Cf sources

1999 ◽  
Vol 26 (1) ◽  
pp. 83-86 ◽  
Author(s):  
R. Schmidt ◽  
R. L. Maughan ◽  
M. Yudelev ◽  
C. Kota ◽  
S. Wanwilairat
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Experimental Determination ◽  
High Intensity ◽  
Thermal Neutron Flux ◽  
Different Types

Determination of thermal neutron flux distribution at the rotary rack served for elemental concentration analysis using the k0-INAA method

2021 ◽  
Vol 10 (1) ◽  
pp. 11-20
Author(s):  
Tho Nguyen Thi ◽  
Anh Tran Tuan ◽  
Cuong Trinh Van ◽  
Doanh Ho Van ◽  
Duong Tran Quoc ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Flux Distribution ◽  
Thermal Neutron Flux ◽  
Epithermal Neutron ◽  
Epithermal Neutron Flux ◽  
Irradiation Position ◽  
Neutron Flux Distribution ◽  
Sample Irradiation

The accuracy of elements concentration determination using the k0-standardization method directly depends on irradiation and measurement parameters including Non-1/E epithermal neutron flux distribution shape α (ϕ epi ≈1/E1+α ) , thermal-to-epithermal neutron flux ratio f, efficiency ε, peak area… In the case of the irradiation position at the rotary rack of the Dalat Nuclear Research Reactor (DNRR), the difference of thermal neutron flux between the bottom (3.54x1012 n.cm-2.s-1) and the top (1.93x1012 n.cm-2.s-1) of the 15 cm aluminum container is up to 45%. Therefore, it is necessary to accurately determine above-mentioned parameters in the sample irradiation position. The present paper deals with the determination of the distribution of thermal neutron flux along the sample irradiation container by using 0.1% Au–Al wire activation technique. The thermal neutron flux was then used to calculate the concentration of elements in the Standard Reference Material 2711a and SMELS type III using k0-INAA method at different positions in the container. The obtained results with the neutron flux correction were found to be in good agreement with the certified values. In conclusion, the proposed technique can be applied for activation analyses without sandwiching flux monitors between samples during irradiations.

scholarly journals Determination of the Thermal Neutron Flux by Measuring Gamma Radiations with High and Low Resolution Detectors

2019 ◽  
Vol 6 (2) ◽  
pp. 187-193
Author(s):  
M. M. Hosamani ◽  
A. S. Bennal ◽  
N. M. Badiger
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Thermal Neutron Flux ◽  
High Energy ◽  
High Energy Resolution ◽  
Indium Foil ◽  
Hpge Detectors ◽  
Foil Activation ◽  
Gamma Radiations

Thermal neutron flux (Фth) of Americium-Beryllium (Am-Be) neutron source has been measured by adopting the foil activation method. The neutrons emitted from Am-Be source are used to activate the indium-115 (115In) foil. The gamma radiations emitted from the activated isomer 116m1In are measured with NaI(Tl) and HPGe detectors. The thermal neutron flux is measured by adopting the cadmium (Cd) foil difference technique in which the Cd foil placed in front of the source to prevent the thermal neutrons from entering into the indium foil. The neutron flux is determined by measuring the gamma radiation emitted from indium foil using a low and high energy resolution NaI(Tl) and HPGe detectors respectively. The measured thermal neutron flux obtained from both detectors has been compared and found that the Фth does not depend on the resolution and type of the detectors used in the present investigations.

Sign in / Sign up

Export Citation Format

Share Document