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As robotics become more sophisticated, there are a growing number of generic systems being used for routine tasks in nuclear environments to reduce risk to radiation workers. The nuclear sector has called for more commercial-off-the-shelf (COTS) devices and components to be used in preference to nuclear specific hardware, enabling robotic operations to become more affordable, reliable, and abundant. To ensure reliable operation in nuclear environments, particularly in high-gamma facilities, it is important to quantify the tolerance of electronic systems to ionizing radiation. To deliver their full potential to endusers, mobile robots require sophisticated autonomous behaviors and sensing, which requires significant computational power. A popular choice of computing system, used in low-cost mobile robots for nuclear environments, is the UP Core single board computer. This work presents estimates of the total ionizing dose that the UP Core running the Robot Operating System (ROS) can withstand, through gamma irradiation testing using a Co-60 source. The units were found to fail on average after 111.1 ± 5.5 Gy, due to faults in the on-board power management circuitry. Its small size and reasonable radiation tolerance make it a suitable candidate for robots in nuclear environments, with scope to use shielding to enhance operational lifetime.

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기사명 저자명 페이지 원문 목차
Front-end investigations of the coated particles of nuclear fuel samples : ion polishing method Zuzanna M. Krajewska, Tomasz Buchwald, Tomasz Tokarski, Wacław Gudowski p. 1935-1946

Effect of surface quality on hydrogen/helium irradiation behavior in tungsten Hongyu Chen, Qiu Xu, Jiahuan Wang, Peng Li, Julong Yuan, Binghai Lyu, Jinhu Wang, Kazutoshi Tokunaga, Gang Yao, Laima Luo, Yucheng Wu p. 1947-1953

Corrosion behavior of refractory metals in liquid lead at 1000 ºC for 1000 h Zunqi Xiao, Jing Liu, Zhizhong Jiang, Lin Luo p. 1954-1961

Corrosion behavior and mechanism of CLAM and 316L steels in flowing Pbe17Li alloy under magnetic field Zunqi Xiao, Jing Liu, Zhizhong Jiang, Lin Luo, Qunying Huang p. 1962-1971

Effects of pulsed laser surface remelting on microstructure, hardness and lead-bismuth corrosion behavior of a ferrite/martensitic steel Hao Wang, Qian Yuan, Linjiang Chai, Ke Zhao, Ning Guo, Jun Xiao, Xing Yin, Bin Tang, Yuqiong Li, Shaoyu Qiu p. 1972-1981

Experimental evaluation of fuel rod pattern analysis in fuel assembly using Yonsei single-photon emission computed tomography (YSECT) Hyung-joo Choi, Bo-Wi Cheon, Min Kyu Baek, Heejun Chung, Yong Hyun Chung, Sei Hwan You, Chul Hee Min, Hyun Joon Choi p. 1982-1990

Hydrothermal synthesis, structure and sorption performance to cesium and strontium ions of nanostructured magnetic zeolite composites Artur Dran'kov, Oleg Shichalin, Evgeniy Papynov, Alexey Nomerovskii, Vitaliy Mayorov, Vladimir Pechnikov, Andrei Ivanets, Igor Buravlev, Sofiya Yarusova, Alexey Zavjalov, Aleksey Ognev, Valeriya Balybina, Aleksey Lembikov, Ivan Tananaev, Nikolay Shapkin p. 1991-2003

Plutonium mass estimation utilizing the (α,n) signature in mixed electrochemical samples Stephen N. Gilliam, Jamie B. Coble, Braden Goddard p. 2004-2010

Development of a method for securing the operator's situation awareness from manipulation attacks on NPP process data Chanyoung Lee, Jae Gu Song, Cheol Kwon Lee, Poong Hyun Seong p. 2011-2022

Multi-channel analyzer based on a novel pulse fitting analysis method Qingshan Wang, Xiongjie Zhang, Xiangting Meng, Bao Wang, Dongyang Wang, Pengfei Zhou, Renbo Wang, Bin Tang p. 2023-2030

Fault injection and failure analysis on Xilinx 16 nm FinFET Ultrascale+ MPSoC Weitao Yang, Yonghong Li, Chaohui He p. 2031-2036

Empirical estimation of human error probabilities based on the complexity of proceduralized tasks in an analog environment Jinkyun Park, Hee Eun Kim, Inseok Jang p. 2037-2047

Uncertainty quantification of the power control system of a small PWR with coolant temperature perturbation Xiaoyu Li, Chuhao Li, Yang Hu, Yongqi Yu, Wenjie Zeng, Haibiao Wu p. 2048-2054

Adaptive undervoltage protection scheme for safety bus in nuclear power plants Choong-koo Chang p. 2055-2061

(The) relationship between public acceptance of nuclear power generation and spent nuclear fuel reuse : implications for promotion of spent nuclear fuel reuse and public engagement Seungkook Roh, Dongwook Kim p. 2062-2066

Graded approach to determine the frequency and difficulty of safety culture attributes : the F-D matrix Jeeyea Ahn, Byung Joo Min, Seung Jun Lee p. 2067-2076

Theoretical simulation on evolution of suspended sodium combustion aerosols characteristics in a closed chamber Sujatha Pavan Narayanam, Amit Kumar, Usha Pujala, Subramanian V., Srinivas C.V., Venkatesan R., Athmalingam S., Venkatraman B p. 2077-2083

Theoretical approach for uncertainty quantification in probabilistic safety assessment using sum of lognormal random variables Gyun Seob Song, Man Cheol Kim p. 2084-2093

Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor Yugao Ma, Jiusong Liu, Hongxing Yu, Changqing Tian, Shanfang Huang, Jian Deng, Xiaoming Chai, Yu Liu, Xiaoqiang He p. 2094-2106

(An) improved regularized particle filter for remaining useful life prediction in nuclear plant electric gate valves Ren-yi Xu, Hang Wang, Min-jun Peng, Yong-kuo Liu p. 2107-2119

Numerical evaluation of hypothetical core disruptive accident in fullscale model of sodium-cooled fast reactor Zhihong Guo, Xiaodong Chen, Guoqing Hu p. 2120-2134

Physical protection system vulnerability assessment of a small nuclear research reactor due to TNT-shaped charge impact on its reinforced concrete wall Jee Hoon Moo, Sunil S. Chirayath, Sung Gook Cho p. 2135-2146

Beyond design basis seismic evaluation of underground liquid storage tanks in existing nuclear power plants using simple method Shen Wang p. 2147-2155

(The) optimum steel fiber reinforcement for prestressed concrete containment under internal pressure Zhi Zheng, Ye Sun, Xiaolan Pan, Chunyang Su, Jingchang Kong p. 2156-2172

(An) investigation into the thermo-elasto-hydrodynamic effect of notched mechanical seals Xiangkai Meng, Yujie Qiu, Yi Ma, Xudong Peng p. 2173-2187

Thermal stress intensity factor solutions for reactor pressure vessel nozzles Si-Hwa Jeong, Kyung-Seok Chung, Wan-Jun Ma, Jun-Seog Yang, Jae-Boong Choi, Moon Ki Kim p. 2188-2197

Radiation tolerance of a small COTS single board computer for mobile robots Andrew West, Jordan Knapp, Barry Lennox, Steve Walters, Stephen Watts p. 2198-2203

Super-spatial resolution method combined with the maximumlikelihood expectation maximization (MLEM) algorithm for alpha imaging detector Guna Kim, Ilhan Lim, Kanghyon Song, Jong-Guk Kim p. 2204-2212

Performance prediction of gamma electron vertex imaging (GEVI) system for interfractional range shift detection in spot scanning proton therapy Sung Hun Kim, Jong Hwi Jeong, Youngmo Ku, Jaerin Jung, Chan Hyeong Kim p. 2213-2220

Research on the optimization method for PGNAA system design based on signal-to-noise ratio evaluation JiaTong Li, WenBao Jia, DaQian Hei, Zeen Yao, Can Cheng p. 2221-2229

Assessment of natural radionuclides and heavy metals contamination to the environment : case study of Malaysian unregulated tin-tailing processing industry Muhammad Abdullah Rahmat, Aznan Fazli Ismail, Nursyamimi Diyana Rodzi, Eli Syafiqah Aziman, Wan Mohd Razi Idris, Tukimat Lihan p. 2230-2243

Geoinformation decision support system for remediation of the 137Cs contaminated agricultural lands after the Chernobyl NPP accident Igor Evgenievich Titov, Viktor Vladimirovich Krechetnikov, Rena Aleksandrovna Mikailova, Aleksei Valerievich Panov p. 2244-2252

Enhancement and optimization of gamma radiation shielding by doped nano HgO into nanoscale bentonite Elhassan A. Allam, Rehab M. El-Sharkawy, Atef El-Taher, E.R. Shaaban, RedaElsaman, E. El Sayed Massoud, Mohamed E. Mahmoud p. 2253-2261

Conceptual design of a copper-bonded steam generator for SFR and the development of its thermal-hydraulic analyzing code Sunghyuk Im, Yohan Jung, Jonggan Hong, Sun Rock Choi p. 2262-2275

Investigation of subcooled boiling wall closures at high pressure using a two-phase CFD code Yazan Alatrash, Yun Je Cho, Chul-Hwa Song, Han Young Yoon p. 2276-2296

Application of the machine learning technique for the development of a condensation heat transfer model for a passive containment cooling system Dong Hyun Lee, Jee Min Yoo, Hui Yung Kim, Dong Jin Hong, Byong Jo Yun, Jae Jun Jeong p. 2297-2310

(The) effects of activated cooler power on the transient pressure decay and helium mixing in the PANDA facility R. Kapulla, S. Paranjape, M. Fehlmann, S. Suter, U. Doll, D. Paladino p. 2311-2320

Numerical study on CMT boron replenishment strategy for an AP1000 nuclear power unit Hong Wang, Miao Zhang, Jialong Li, Junpeng Wang p. 2321-2328

Electrochemical corrosion study on base metals used in nuclear power plants in the HyBRID process for chemical decontamination Sung-Wook Kim, Sang-Yoon Park, Chang-Hyun Roh, Ji-Hyung Shim, Sun-Byeong Kim p. 2329-2333

Estimation of the neutron production of KSTAR based on empirical scaling law of the fast ion stored energy and ion density under NBI power and machine size upgrade Jong-Gu Kwak, S.C. Hong p. 2334-2337

참고문헌 (36건) : 자료제공( 네이버학술정보 )

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