scholarly journals The Impact of Successive Gamma and Neutron Irradiation on Characteristics of PIN Photodiodes and Phototransistors

10.5772/62756 ◽  
2016 ◽  
Author(s):  
Dejan Nikolić ◽  
Aleksandra Vasić-Milovanović
Keyword(s):  
Neutron Irradiation ◽  
Pin Photodiodes ◽  
The Impact

The effect of neutron irradiation on the impact toughness of austenitic stainless steel in ultrafine-grained state

2021 ◽  
Vol 544 ◽  
pp. 152680
Author(s):  
Valentin K. Shamardin ◽  
Tatyana M. Bulanova ◽  
Alexander E. Fedoseev ◽  
Alexei A. Karsakov ◽  
Ruslan Z. Valiev ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Impact Toughness ◽  
Neutron Irradiation ◽  
Ultrafine Grained ◽  
The Impact

The impact of reactor neutron irradiation on total ionizing dose degradation in MOSFET

2019 ◽  
Vol 924 ◽  
pp. 245-249
Author(s):  
Chenhui Wang ◽  
Xiaoming Jin ◽  
Wei Chen ◽  
Shanchao Yang ◽  
Yan Liu ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Reactor Neutron ◽  
Total Ionizing Dose ◽  
The Impact ◽  
Reactor Neutron Irradiation

The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

2013 ◽  
Author(s):  
Xiang Fang ◽  
Haitao Wang ◽  
Xingtuan Yang ◽  
Suyuan Yu
Keyword(s):  
High Temperature ◽  
Neutron Irradiation ◽  
Three Dimensional ◽  
Reactor Core ◽  
Neutron Dose ◽  
Element Analysis ◽  
The Core ◽  
Three Dimensional Finite Element ◽  
Dose Levels ◽  
The Impact

In high temperature gas-cooled reactors (HTRs), graphite is used as the main structure material. The side reflecter of the reactor core is composed by a pile of graphite bricks. In real operational condition of the reactor, both high temperature and fast neutron irradiation have great effect on the behavior of graphite components. The non-uniform distribution of temperature and neutron dose cause obvious stress accumulation, which greatly affects the security and reliability of the graphite components. In addition, high temperature and neutron irradiation make the properties of graphite change in evidence, and the changes are not linear. Such changes must be considered and simulated in the calculation, in order to predict the stress concentration condition and the reliability of the graphite brick correctly. A FORTRAN code based on user subroutines of MSC.MARC is developed in INET in order to perform three-dimensional finite element analysis of irradiated behavior of the graphite components for the HTRs. In this paper, the stress level and failure probability of graphite components are calculated and obtained under different in-core temperatures and neutron dose levels of the core side of brick. 400°C, 500°C, 600°C and 700°C are selected as the core side temperature, while the range of neutron dose is 0 to 1022n cm-2 (EDN). Different constitutive laws are used in stress analysis procedure. The impact of different temperature and neutron dose levels are discussed.

Degradation of InGaAs pin photodiodes by neutron irradiation

1996 ◽  
Vol 11 (10) ◽  
pp. 1461-1463 ◽  
Author(s):  
H Ohyama ◽  
J Vanhellemont ◽  
Y Takami ◽  
K Hayama ◽  
T Kudou ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Pin Photodiodes

Cyclic Crack Growth Rate of Irradiated Austenitic Stainless Steel Welds in Simulated BWR Environment

2011 ◽  
Author(s):  
Y. Chen ◽  
B. Alexandreanu ◽  
W. J. Shack ◽  
K. Natesan ◽  
A. S. Rao
Keyword(s):  
Stainless Steel ◽  
Austenitic Stainless Steel ◽  
Crack Growth ◽  
Neutron Irradiation ◽  
Growth Rates ◽  
Reactor Core ◽  
Cracking Behavior ◽  
Steel Welds ◽  
The Impact ◽  
Crack Growth Rates

Reactor core internal components in light water reactors are subjected to neutron irradiation. It has been shown that the austenitic stainless steels used in reactor core internals are susceptible to stress corrosion cracking after extended neutron exposure. This form of material degradation is a complex phenomenon that involves concomitant conditions of irradiation, stress, and corrosion. Interacting with fatigue damage, irradiation-enhanced environmental effects could also contribute to cyclic crack growth. In this paper, the effects of neutron irradiation on cyclic cracking behavior were investigated for austenitic stainless steel welds. Post-irradiation cracking growth tests were performed on weld heat-affected zone specimens in a simulated boiling water reactor environment, and cyclic crack growth rates were obtained at two doses. Environmentally enhanced cracking was readily established in irradiated specimens. Crack growth rates of irradiated specimens were significantly higher than those of nonirradiated specimens. The impact of neutron irradiation on environmentally enhanced cyclic cracking behavior is discussed for different load ratios.

scholarly journals Systematic Electro-Optical Study of Photodiodes in Intrinsic Material (Lowly Doped) with Backend Stack Optimization

Proceedings ◽  
2018 ◽  
Vol 2 (13) ◽  
pp. 909
Author(s):  
Frederic Roger ◽  
Ingrid Jonak-Auer ◽  
Olesia Synooka ◽  
Filip Segmanovic ◽  
Joni Mellin ◽  
...  
Keyword(s):  
Silicon Surface ◽  
Spectral Response ◽  
Optical Study ◽  
Optical Performance ◽  
Reflective Coating ◽  
Pin Photodiode ◽  
Type Layer ◽  
P Type ◽  
Pin Photodiodes ◽  
The Impact

This paper constitutes the analysis of the impact of low doped intrinsic p-type EPI thickness (20 µm and 30 µm) and bottom anti-reflective coating on the electrical and optical performance of various PIN photodiodes designs. The intrinsic p-type layer with a target resistivity of 400 Ω cm is an epitaxial layer (iEPI) grown on a low resistive substrate of 20 mΩ cm. Optimization of the photodiode’s spectral responsivity (for a specific wavelength) includes a Bottom Anti-Reflective Coating (BARC) layer deposited over the silicon surface. BARC thickness is optimized for λ = 425 nm, λ = 750 nm and λ = 900 nm wavelengths. With respective BARC in place, the photodiode’s quantum efficiency (QE) approaches 100% for λ = 750 nm with 20 µm and 30 µm iEPI thickness and for λ = 900 nm with 30 µm iEPI reaching also a maximum spectral response of 0.63 A/W at 800 nm. QE of 72% could be achieved at 425 nm. The leakage current varies from 3.5 pA for 20 µm iEPI thickness to 10 pA for 30 µm at 1 V reverse biasing for 365 µm circular PIN photodiode.

scholarly journals The Impact of Dose Rate on DNA Double-Strand Break Formation and Repair in Human Lymphocytes Exposed to Fast Neutron Irradiation

2019 ◽  
Vol 20 (21) ◽  
pp. 5350 ◽  
Author(s):  
Shankari Nair ◽  
Monique Engelbrecht ◽  
Xanthene Miles ◽  
Roya Ndimba ◽  
Randall Fisher ◽  
...  
Keyword(s):  
Dna Damage ◽  
Dose Rate ◽  
Neutron Irradiation ◽  
Low Dose ◽  
Human Lymphocytes ◽  
Strand Break ◽  
Double Strand Break ◽  
Low Dose Rate ◽  
Dna Double Strand Break ◽  
The Impact

The lack of information on how biological systems respond to low-dose and low dose-rate exposures makes it difficult to accurately assess the carcinogenic risks. This is of critical importance to space radiation, which remains a serious concern for long-term manned space exploration. In this study, the γ-H2AX foci assay was used to follow DNA double-strand break (DSB) induction and repair following exposure to neutron irradiation, which is produced as secondary radiation in the space environment. Human lymphocytes were exposed to high dose-rate (HDR: 0.400 Gy/min) and low dose-rate (LDR: 0.015 Gy/min) p(66)/Be(40) neutrons. DNA DSB induction was investigated 30 min post exposure to neutron doses ranging from 0.125 to 2 Gy. Repair kinetics was studied at different time points after a 1 Gy neutron dose. Our results indicated that γ-H2AX foci formation was 40% higher at HDR exposure compared to LDR exposure. The maximum γ-H2AX foci levels decreased gradually to 1.65 ± 0.64 foci/cell (LDR) and 1.29 ± 0.45 (HDR) at 24 h postirradiation, remaining significantly higher than background levels. This illustrates a significant effect of dose rate on neutron-induced DNA damage. While no significant difference was observed in residual DNA damage after 24 h, the DSB repair half-life of LDR exposure was slower than that of HDR exposure. The results give a first indication that the dose rate should be taken into account for cancer risk estimations related to neutrons.

scholarly journals Effect of neutron irradiation on the impact properties of A533B steel

1994 ◽  
Author(s):  
L.E. Schubert ◽  
A.S. Kumar ◽  
S.T. Rosinski ◽  
M.L. Hamilton
Keyword(s):  
Neutron Irradiation ◽  
Impact Properties ◽  
The Impact
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