scholarly journals Characterization of the Secondary Neutron Field Produced in a Thick Aluminum Shield by 1 GeV/u 56Fe Ions Using TLD-Based Ambient Dosimeters

2020 ◽  
Vol 8 ◽  
Author(s):  
Daria Boscolo ◽  
Daniela Scognamiglio ◽  
Felix Horst ◽  
Uli Weber ◽  
Christoph Schuy ◽  
...  
Keyword(s):  
Neutron Field ◽  
Secondary Neutron

Characterization of the secondary neutron field produced during treatment of an anthropomorphic phantom with x-rays, protons and carbon ions

2014 ◽  
Vol 59 (8) ◽  
pp. 2111-2125 ◽  
Author(s):  
C La Tessa ◽  
T Berger ◽  
R Kaderka ◽  
D Schardt ◽  
S Burmeister ◽  
...  
Keyword(s):  
Neutron Field ◽  
X Rays ◽  
Carbon Ions ◽  
Anthropomorphic Phantom ◽  
Secondary Neutron

scholarly journals Characterization of the gamma flux in a tangential channel of the CENM TRIGA MARK II research reactor

2020 ◽  
Vol 225 ◽  
pp. 04030
Author(s):  
A. Gruel ◽  
D. Fourmentel ◽  
C. El Younoussi ◽  
B. El Bakkari ◽  
Y. Boulaich ◽  
...  
Keyword(s):  
Steady State ◽  
Nuclear Data ◽  
Neutron Field ◽  
Photon Propagation ◽  
The Core ◽  
Thermal Maximum ◽  
Gamma Field ◽  
Triga Mark Ii ◽  
Gamma Flux

The CNESTEN (National Center for Energy Sciences and Nuclear Technology, Morocco) operates a TRIGA Mark II reactor, which can reach a thermal maximum power at steady state of 2 MW. In reactors devoted to research and experiments, it is mandatory to characterize the neutron and photon fields in the irradiation positions. Together with a computational model of the core, it ensures the ability to reach the requested uncertainties when performing experiments, such as detectors testing, irradiation for hardening or nuclear data measurements. The neutron field of different irradiation positions has been characterized by dosimetry techniques and compared to the MCNP full model of the reactor. Preliminary photon propagation calculations are also performed with this model, but up to now, no experimental validation of the results exists. The aim of the newly set collaboration between CEA and CNESTEN is to characterize the gamma field of these positions. The first position investigated is the part of the NB1 tangential channel closest to the core. Among gamma measurements techniques, and according to the constraints arising from using this channel, it was chosen to use thermos- and optically stimulated luminescent detectors. This paper presents the experiments carried out in September 2018 as well as their results. Three detectors types were used: TLD400 (CaF2:Mn), TLD700 (7LiF:Mg,Ti) and OSLD (Al2O3:C). Measurements were performed in several steps: background measurements, transient measurements (divergence phase + SCRAM), and irradiation at steady state. In the end, these measurements will provide a dose as well as a gamma flux value for this position.

Characterization of 235U Targets for the Development of a Secondary Neutron Fluence Standard

2014 ◽  
Vol 119 ◽  
pp. 407-409 ◽  
Author(s):  
J. Heyse ◽  
M. Anastasiou ◽  
R. Eykens ◽  
A. Moens ◽  
A.J.M. Plompen ◽  
...  
Keyword(s):  
Neutron Fluence ◽  
Secondary Neutron

scholarly journals The CANDELLE experiment for characterization of neutron sensitivity of LiF TLDs

2018 ◽  
Vol 170 ◽  
pp. 04014 ◽  
Author(s):  
M.Le Guillou ◽  
A. Billebaud ◽  
A. Gruel ◽  
G. Kessedjian ◽  
O. Méplan ◽  
...  
Keyword(s):  
Neutron Field ◽  
Early Assessment ◽  
Power Flux ◽  
Design Studies ◽  
Thermoluminescent Dosimeters ◽  
Highly Sensitive ◽  
Gamma Field ◽  
Nuclear Heating

As part of the design studies conducted at CEA for future power and research nuclear reactors, the validation of neutron and photon calculation schemes related to nuclear heating prediction are strongly dependent on the implementation of nuclear heating measurements. Such measurements are usually performed in low-power reactors, whose core dimensions are accurately known and where irradiation conditions (power, flux and temperature) are entirely controlled. Due to the very low operating power of such reactors (of the order of 100 W), nuclear heating is assessed by using dosimetry techniques such as thermoluminescent dosimeters (TLDs). However, although they are highly sensitive to gamma radiation, such dosimeters are also, to a lesser extent, sensitive to neutrons. The neutron dose depends strongly on the TLD composition, typically contributing to 10-30% of the total measured dose in a mixed neutron/gamma field. The experimental determination of the neutron correction appears therefore to be crucial to a better interpretation of doses measured in reactor with reduced uncertainties. A promising approach based on the use of two types of LiF TLDs respectively enriched with lithium-6 and lithium-7, precalibrated both in photon and neutron fields, has been recently developed at INFN (Milan, Italy) for medical purposes. The CANDELLE experiment is dedicated to the implementation of a pure neutron field “calibration” of TLDs by using the GENEPI-2 neutron source of LPSC (Grenoble, France). Those irradiation conditions allowed providing an early assessment of the neutron components of doses measured in EOLE reactor at CEA Cadarache with 10% uncertainty at 1σ.

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