Determination of neutron spectra within the energy of 1 keV to 1 MeV by means of reactor dosimetry

2015 ◽  
Author(s):  
V. Sergeyeva ◽  
N. Thiollay ◽  
O Vigneau ◽  
G. Korschinek ◽  
H. Carcreff ◽  
...  
Keyword(s):  
Neutron Spectra ◽  
Reactor Dosimetry

Determination of Neutron Spectra Within the Energy of 1 keV to 1 MeV by Means of Reactor Dosimetry

2015 ◽  
pp. 1-8 ◽  
Author(s):  
V. Sergeyeva ◽  
N. Thiollay ◽  
O. Vigneau ◽  
G. Korschinek ◽  
H. Carcreff ◽  
...  
Keyword(s):  
Neutron Spectra ◽  
Reactor Dosimetry

scholarly journals Impact of the cross section library on 93mNb activity in VVER-1000 reactor dosimetry

2020 ◽  
Vol 225 ◽  
pp. 03009
Author(s):  
P. Haroková ◽  
M. Lovecký
Keyword(s):  
Cross Section ◽  
Neutron Transport ◽  
Nuclear Data ◽  
Nuclear Data Library ◽  
The Cross ◽  
Materials Used ◽  
The Impact ◽  
Data Library ◽  
Reactor Dosimetry

One of the objectives of reactor dosimetry is determination of activity of irradiated dosimeters, which are placed on reactor pressure vessel surface, and calculation of neutron flux in their position. The uncertainty of calculation depends mainly on the choice of nuclear data library, especially cross section used for neutron transport and cross section used as the response function for neutron activation. Nowadays, number of libraries already exists and can be still used in some applications. In addition, new nuclear data library was recently released. In this paper, we have investigated the impact of the cross section libraries on activity of niobium, one of the popular materials used as neutron fluence monitor. For this purpose, a MCNP6 model of VVER-1000 was made and we have compared the results between 14 commonly used cross section libraries. A possibility of using IRDFF library in activation calculations was also considered. The results show good agreement between the new libraries, with the exception of the most recent ENDF/B-VIII.0, which should be further validated.

Determination of cyclotron fast neutron spectra and fluxes with activation detectors

Physica ◽  
1964 ◽  
Vol 30 (5) ◽  
pp. 978-984 ◽  
Author(s):  
I. Heertje ◽  
A.H.W. Aten
Keyword(s):  
Fast Neutron ◽  
Neutron Spectra

Determination of neutron generator fast neutron spectra using threshold detectors

1980 ◽  
Vol 178 (2-3) ◽  
pp. 451-458 ◽  
Author(s):  
Mervi Hyvönen-Dabek ◽  
Päivi Nikkinen-Vilkki
Keyword(s):  
Fast Neutron ◽  
Neutron Generator ◽  
Neutron Spectra

scholarly journals NEUTRON RESPONSE FUNCTION OF BONNER SPHERE SPECTROMETER WITH 6LiI(Eu) DETECTOR

2017 ◽  
Vol 20 (2) ◽  
pp. 65 ◽  
Author(s):  
Rasito Tursinah ◽  
Bunawas Bunawas ◽  
Jungho Kim
Keyword(s):  
Monte Carlo ◽  
Response Function ◽  
Neutron Fluence ◽  
Detector Response ◽  
Response Functions ◽  
Neutron Spectra ◽  
Mcnpx Code ◽  
Bonner Sphere ◽  
Bonner Sphere Spectrometer

Neutron Response Function of Bonner Sphere Spectrometer With 6LiI(Eu) Detector. The detector response function was needed to measure the neutron fluence based on the count rates from Bonner Sphere Spectrometer (BSS). The determination of response function of a BSS with 6LiI(Eu) detector has been performed using Monte Carlo MCNPX code. This calculation was performed for BSS using scintillation detector of 4 mm × 4 mm 6LiI(Eu) which is placed at the center of a set of polyethylene spheres i.e bare, 2", 3", 5", 8", 10", and 12" diameters. The BSS response functions were obtained for neutron energy of 1x10-9 MeV - 1x102  MeV in 111 energy bins and each value has an uncertainty less or equal to 2 %. The response function were compared with two response functions reported in the literature i.e IAEA document in Technical Reports Series 403 (TRS-403) and the calculation from Vega-Carrillo, et al. Also validated with measurement 252Cf neutron spectra, that shown the simulated BSS spectra were quite close to the experimental measured with a differrence of 3%.

Determination of Adjusted Neutron Spectra in Different MUSE Configurations by Unfolding Techniques

2006 ◽  
Vol 3 (3) ◽  
pp. 13443
Author(s):  
M Plaschy ◽  
C Destouches ◽  
R Chawla ◽  
D Beretz ◽  
F Mellier ◽  
...  
Keyword(s):  
Neutron Spectra

DETERMINATION OF NEUTRON SPECTRA IN A MOX PLANT FOR THE QUALIFICATION OF THE BD-PND BUBBLE DETECTOR

1999 ◽  
Vol 77 (2) ◽  
pp. 200-206 ◽  
Author(s):  
R. Olaerts ◽  
P. Kockerols ◽  
A. Renard ◽  
W. Rosenstock ◽  
T. Köble ◽  
...  
Keyword(s):  
Neutron Spectra

scholarly journals An investigation of the neutrons produced in the deuteron-deuteron reaction

1948 ◽  
Vol 195 (1040) ◽  
pp. 123-134 ◽  
Keyword(s):  
Angular Distribution ◽  
Neutron Emission ◽  
Photographic Plate ◽  
Deuteron Beam ◽  
Forward Direction ◽  
Maximum Energy ◽  
Neutron Spectra ◽  
Precision Determination ◽  
Good Agreement

Some properties of the 2 1 H + 2 1 H = 2 He+ 1 0 n reaction are investigated by the photographic plate technique for a bombarding deuteron energy of 920 keV. Thick deuterium targets only are used, and the following quantities measured : ( a ) The Q value—found to be (3·23 ± 0·02) MeV. ( b ) The neutron spectra at various angles of neutron emission. ( c ) The angular distribution of the neutrons. The problems arising in the application of the technique to the precision determination of neutron energy are discussed and the previous precision determination of the Q value by Bonner is criticized. The present results are in good agreement with the Q value of the reaction 2 1 H + 2 1 H = 3 1 H + 1 1 H and the maximum energy of the 3 1 H β-spectrum. The neutron spectra are in accord with those calculated from the ballistics of the reaction and the known excitation function. The neutron angular distribution shows a marked maximum in the forward direction and a minimum at 90° to the deuteron beam.

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