Lanthanum Halide and Cerium Bromide Scintillators

2017 ◽  
pp. 261-284
Author(s):  
Oliver J. Roberts
Keyword(s):  
2017 ◽  
Vol 60 (6) ◽  
pp. 1307-1314 ◽  
Author(s):  
D.K. Panda ◽  
D. Banerjee ◽  
S.K. Goyal ◽  
A.R. Patel ◽  
A.D. Shukla

2017 ◽  
Vol 52 (6) ◽  
pp. 1600401 ◽  
Author(s):  
Tomoki Ito ◽  
Yuui Yokota ◽  
Shunsuke Kurosawa ◽  
Kei Kamada ◽  
Yuji Ohashi ◽  
...  

2018 ◽  
Vol 318 (1) ◽  
pp. 533-542
Author(s):  
Thomas Scott ◽  
Kelly Garnick ◽  
Elon Malkin ◽  
Jennifer Szymanski ◽  
Cong Wei ◽  
...  
Keyword(s):  
Γ Ray ◽  

Author(s):  
Toshiyuki Onodera ◽  
Keitaro Hitomi ◽  
Tadayoshi Shoji

2018 ◽  
Vol 170 ◽  
pp. 06004
Author(s):  
M. Nancekievill ◽  
A. R. Jones ◽  
M. J. Joyce ◽  
B. Lennox ◽  
S. Watson ◽  
...  

This paper describes the development of a submersible system based on a remote-operated vehicle coupled with radiation detectors to map the interior of the reactors at the Fukushima Daiichi nuclear power station. It has the aim oflocating fuel debris. The AVEXIS submersible vehicle used in this study has been designed as a low-cost, potentially disposable, inspection platform that is the smallest of its class and is capable of being deployed through a 150 mm diameter access pipe. To map the gamma-ray environment, a cerium bromide scintillator detector with a small form factor has been incorporated into the AVEXIS to identify radioactive isotopes via gamma-ray spectroscopy. This provides the combined system with the potential to map gamma-ray spectra and particle locations throughout submerged, contaminated facilities, such as Units 1, 2 and 3 of the Fukushima Daiichi nuclear power plant. The hypothesis of this research is to determine the sensitivity of the combined system in a submerged environment that replicates the combination of gamma radiation and water submersion but at lower dose rates.


2019 ◽  
Vol 204 ◽  
pp. 12-20 ◽  
Author(s):  
Christos Tsabaris ◽  
Effrossyni G. Androulakaki ◽  
Aristides Prospathopoulos ◽  
Stylianos Alexakis ◽  
Georgios Eleftheriou ◽  
...  

2020 ◽  
Vol 225 ◽  
pp. 04016 ◽  
Author(s):  
O. Pakari ◽  
V. Lamirand ◽  
B. Vandereydt ◽  
F. Vitullo ◽  
M. Hursin ◽  
...  

Gamma rays in nuclear reactors, arising either from fission or decay processes, significantly contribute to the heating and dose of the reactor components. Zero power research reactors offer the possibility to measure gamma rays in a purely neutronic environment, allowing for validation experiments of computed spectra, dose estimates, reactor noise and prompt to delayed gamma ratios. This data then contributes to models, code validation and photo atomic nuclear data evaluation. In order to contribute to aforementioned experimental data, gamma detection capabilities are being added to the CROCUS reactor facility. The CROCUS reactor is a two-zone, uranium-fueled light water moderated facility operated by the Laboratory for Reactor Physics and Systems Behaviour (LRS) at the Swiss Federal Institute of Technology Lausanne (EPFL). With a maximum power of 100W, it is a zero power reactor used for teaching and research, most recently for intrinsic and induced neutron noise studies. For future gamma detection applications in the CROCUS reactor, an array of four detectors - two large 5”x10” Bismuth Germanate (BGO) and two smaller Cerium Bromide (CeBr3) scintillators - was acquired. The BGO detectors are to be arbitrarily positioned in the core reflector and out of the vessel for measurements at arbitrary distances. The CeBr3 detectors on the other hand are small enough to be set in the guide tubes of the control rods for in-core measurements. We present a study of the neutron and gamma flux in the core and reflector using the MCNP 6.2 and Serpent 2 Monte Carlo codes for coupled neutron and photon transport criticality calculations. More specifically, we investigate and compare predicted spectra as well as reactivity worth of different envisioned experimental setups. We further predict pulse height spectra as well as doses to the crystals with and without cadmium shielding to estimate allowable reactor powers with respect to detector radiation hardness. The results serve as basis for calibration and aid in the design and regulatory approval of the experiments.


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