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Neutronic analysis of Indian helium-cooled solid breeder tritium breeding module for testing in ITER

Plasma Science and Technology 2022年第6期24卷 189-195页

作者： H L SWAMI Deepak SHARMA C DANANI P CHAUDHARI R SRINIVASAN Rajesh KUMAR Institute for Plasma Research Gandhinagar 382428India Homi Bhabha National Institute AnushaktinagarMumbai 400094India

India has proposed the helium-cooled solid breeder blanket concept as a tritium breeding module to be tested in *** module has lithium titanate for tritium breeding and beryllium for neutron *** also enhances tritium breeding.A design for the module is prepared for detailed *** analysis is performed to assess the tritium breeding rate,neutron distribution,and heat distribution in the *** tritium production distribution in submodules is evaluated to support the tritium transport *** tritium breeding density in the radial direction of the module is also assessed for further optimization of the *** heat deposition profile of the entire module is generated to support the heat removal circuit *** estimated neutron spectrum in the radial direction also provides a more in-depth picture of the nuclear interactions inside the material *** total tritium produced in the HCSB module is around 13.87 mg per full day of operation of ITER,considering the 400 s ON time and 1400 s dwell *** estimated nuclear heat load on the entire module is around 474 kW,which will be removed by the high-pressure helium cooling *** heat deposition in the test blanket model(TBM)is huge(around 9 GJ)for an entire day of operation of ITER,which demonstrates the scale of power that can be produced through a fusion reactor *** per the Brayton cycle,it is equivalent to 3.6 GJ of electrical *** terms of power production,this would be around 1655 MWh *** evaluation is carried out using the MCNP5 Monte Carlo radiation transport code and FEDNL 2.1 nuclear cross section *** HCSB TBM neutronic performance demonstrates the tritium production capability and high heat deposition.

关键词： HCSB TBM tritium nuclear heat ITER

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Simulation of the effects of different substrates, temperature,and substrate roughness on the mechanical properties of Al_2O_3 coating as tritium penetration barrier

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Nuclear Science and Techniques 2019年第4期30卷 80-90页

作者： Ze Liu Fei Meng Liang-Bi Yi Key Laboratory for Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu Youfang Technology Co. Ltd Southwestern Institute of Physics

Residual thermal stress in the system is a serious problem that affects the application of tritium permeation barrier coatings in fusion reactors. The stress not only determines the adhesion between coating and substrate, but also changes the properties of the material. In this study,finite element analysis was used to investigate the relationship between the residual thermal stress and the mechanical properties of Al_2O_3 tritium penetration barrier systems. Moreover, the residual thermal stress influenced by factors such as different substrates, temperature, and substrate roughness was also analyzed. The calculation showed that the hardness and elastic modulus increased with increasing compressive stress. However, the hardness and elastic modulus decreased with increasing tensile stress. The systems composed of Al_2O_3 coatings and different substrates exhibited different trends in mechanical properties. As the temperature increased, the hardness and the elastic modulus increased in an Al_2O_3/316 L stainless steel system; the trend was opposite in an Al_2O_3/Si *** from this, the roughness of the substrate surface in the system could magnify the change in hardness and elastic modulus of the coating. Results showed that all these factors led to variation in the mechanical properties of Al_2O_3 tritium permeation barrier systems. Thus, thedetailed reasons for the changes in mechanical properties of these materials need to be analyzed.

关键词： Finite element analysis Thermal stress Mechanical properties Al2O3 tritium penetration barrier systems Nanoindentation

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Distribution characteristics of tritium in the soil in Beishan area of Gansu Province

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Journal of Groundwater Science and Engineering 2016年第2期4卷 131-140页

作者： LI Jie-biao SU Rui YANG Jing-zhi ZHOU Zhi-chao JI Rui-li ZHANG Ming GAO Yu-feng Beijing Research Institute of Uranium Geology Beijing 100029China CNNC Key Laboratory on Geological Disposal of High-level Radioactive Waste Beijing 100029China

Beishan region in Gansu was the preselected area for China's high-level radioactive waste(HLW) repository. In selecting and evaluating a new dump site, the tritium study is of great significance. The Xinchang-Xiangyangshan preselected area in the Beishan area was taken as an example. This paper selects typical unit and tries to use the distribution characteristics of tritium in the soil to study the atmospheric precipitation infiltration recharge in this area. The results show: In this region, the spatial variability of the tritium content in surface soil is large; it is feasible to use bound tritium tracer method to study the theory of atmospheric precipitation infiltration recharge; the atmospheric precipitation infiltration has close relationship with the soil particle composition, salt content, mineral composition, water content and organic matter content. These results can provide important basis for developing the atmospheric precipitation infiltration recharge, groundwater numerical simulation, nuclide migration study and so on.

关键词： tritium Atmospheric precipitation infiltration Free water tritium Bound tritium High-level radioactive waste

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Transient Behavior in Water Distillation Tower for tritium Separation and Its Long-Time Operation Test Results

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Journal of Power and Energy Engineering 2017年第3期5卷 1-17页

作者： Yoshiaki Miho Satoshi Fukada Mitsuki Arimoto Takaho Takeuchi Tomohiro Motomura Junji Mizutani Satoru Hirano Department of Advanced Energy Engineering Science Kyushu University Kasuga Japan Sasakura Engineering Co. Ltd. Osaka Japan

Transient separation behavior in tritiated water distillation tower packed with materials having ability to adsorb water is investigated analytically and experimentally for nuclear reactor safety. Analytical equations based on the stage model are set up for simulation of the transient behavior of tritium (T) separation from wastewater. It is found that a dimensionless time defined in terms of the inside vapor flow rate and the liquid holdups in tower, reboiler and condenser can correlate variations over time to achieve a steady-state T concentration. However, when mixing with different T concentrations at a feed point occurs, the transition time period becomes longer than expected. Effects of the reflux ratio, the stage separation factor and the total stage number on the transient and steady-state T concentrations are numerically calculated. Variations over time to achieve each steady-state value are compared with experimental data using a small-scale tower. Long time distillation experiment for one month has been completed, and it is confirmed that a distillation column packed with ceramic Raschig rings coated with zeolite 13X adsorbent is hardly affected by water corrosion.

关键词： Water Distillation tritium Isotope Separation Transient Analysis Adsorption Wastewater

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Biodegradation of tritium Labeled Polychlorinated Biphenyls (PCBS) by Local Salt Tolerant Mesophylic Bacillus Strains

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Journal of Environmental Protection 2010年第4期1卷 420-425页

作者： Rasulov Bakhtiyor Abdughafurovich Kim Andrey Andreevich Lorenz Adrian Yadgarov Khojiakbar Tashpulatovich Institute of Genetics and Plant Experimental Biology Uzbekistan Academy of Sciences Institute of Nuclear Physics Uzbekistan Academy of Sciences Department Isotope Biogeochemistry Helmholtz Centre for Environmental Research

Salt-resistant Bacillus strains, isolated from agricultural soils in Uzbekistan, were tested for degradation activity towards a mixture of polychlorinated biphenyls (PCBs) under aerobic conditions. The study employed the use of tritium labeled PCB congeners and traced the tritium label in cultures with high salt content. The experiments show that most of the selected strains were able to adsorb a part of the radioactivity, indicating transformation of the added PCBs. Gas chromatography demonstrated transformation of PCBs. The radioactive label was removed from several cultures by up to 91%, indicating also mineralization of PCBs. The study suggests that the isolated strains might be good candidates for the bioremediation of contaminated high-salt soils in Uzbekistan and other Central-Asian countries.

关键词： Bacillus Biodegradation PCBs Salinity tritium Label

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Cytogenetic Effects of Low-Dose Tritiated Water in Human Peripheral Blood Lymphocytes—Experimental Studies on the Relative Biological Effectiveness and Chromosome Aberration Rate and CBMN in Human Blood Lymphocyte Irradiated by tritium Low Dose tritium β-Rays and 60Co γ-Rays

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Open Journal of Clinical Diagnostics 2015年第4期5卷 125-135页

作者： Bing Deng Jingwei Hou Yi Quan Lan Dong Zhaoyi Tan Institute of Nuclear Physics and Chemistry China Academy of Engineering Physics Mianyang China Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions Suzhou China

In this study, the yields of unstable chromosome aberrations in human lymphocytes induced by β particles from low-dose HTO have been measured. HTO was mixed with heparinized blood in varying amounts so that a dose of 6.24 × 10-4 Gy to 1.23 Gy were delivered in 24 and 48 h, respectively. After 72-h culture, the dicentric yield was measured as a function of dose to the blood and compared with data from 60Co γ-radiation. Using a linear-quadratic dose-effect relation to fit the experimental data, a significant linear contribution Y = 0.062D + 0.053D2 was found. The main difference between the coefficients for β and γ-radiation was in the a values, indicating that HTO β-rays were more efficient, particularly at low doses. As per the theory of dual radiation, the relative biological effectiveness (RBE) of HTO β-particles relative to γ-rays is 2.21 at 0.06 Gy and decreases with increasing dose. Micronucleus yield at low doses was fitted to a linear equation Y = C + αD, indicating that the RBE value of MN for HTO β-rays irradiation was between 1.46 and 2.17, which is similar in shape to the chromosome aberrations experiments. Thus, β-rays were found to be more efficient in producing two lesions with single ionizing tracks at low dose.

关键词： tritium β-Radiation Chromosome Aberrations MN RBE

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Determination of tritium Concentration in Heavy Water

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World Journal of Nuclear Science and Technology 2014年第3期4卷 170-176页

作者： Reza Pourimani Mehrdad Aghamohammadi Department of Physics Faculty of Science Arak University Arak Iran

In this work, tritium concentration was determined in different D2O enrichment in heavy water samples. Samples were prepared from Arak Heavy Water Production Plant. tritium concentration was determined utilizing liquid scintillation detector (LSC) system based on β-decay of tritium isotope. In this work instead of simple distillation, the azeotropic distillation method was used. Absorbed spectra and fluorescence spectra were registered by Shimadz spectrometer UV-2100 model and fluorescence spectrometer LS50B model respectively. tritium concentration was obtained from 1.75 ± 0.80 up 6.16 ± 1.01 Bq/L for 0.35% to 77.50% enrichment of D2O concentration in heavy water samples. Coefficient correlation between tritium concentration and D2O concentration in heavy water R2 = 0.853 was derived. For 99.8% enriched D2O in heavy water, deviation was observed from direct line that caused decreasing of R2.

关键词： tritium Liquid Scintillation Detector Heavy Water Correlation Coefficient Azeotropic Distillation

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Estimates of tritium Produced Ratio in the Blanket of Fusion Reactors

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Open Journal of Microphysics 2013年第1期3卷 8-11页

作者： Mohammad Mahdavi Elham Asadi Physics Department Mazandaran University Babolsar Iran

For the preparation of tritium fuel as the main and rare fuel of reactors in the fusion reactors, the reactor blanket must be designed so that it provides enough tritium breeding ratio. The tritium breeding ratio, TBR, in the blanket of reactors should be greater than one, (TBR > 1), by applying lithium blanket. The calculations for proposed parameters (td , fb , η and tp), indicate that the estimated tritium breeding ratio is greater than one. The calculated TBR = 1.04 satisfies the tritium provision condition.

关键词： tritium Breeding Ratio Reactor Blanket Lithium Fusion

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ANALYSIS OF tritium CONTENT IN GLACIER WATER IN HENGDUAN MOUNTAINS

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Chinese Science Bulletin 1988年第13期33卷 1117-1120页

作者：王立伦王平 Lanzhou Institute of Glaciology and Gcocryology Academia Sinica

Glacier is a movable natural icebody formed from the concentration and evolu- tion of solid precipitation. tritium is an ideal tracer for the conversion process of glacier water. The measurement of tritium content in ... 详细信息

关键词： glacier water tritium content Hengduen Mts snowfall meltwater

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Analysis of tritium activity concentrations in urine and internal dose assessment for nuclear power plant workers

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Radiation Medicine and Protection 2021年第1期2卷 1-4页

作者： Fei Chen Xuetao Wang Yuwen Li Zhen Zhang National Center for Occupational Safety and Health National Health CommissionBeijing102308China

Objective:To investigate the activity concentration of tritium in urine of nuclear power plant(NPP)workers,in order to evaluate the occupational exposure ***:Three chosen NPPs were respectively located in southern,southeastern and northeastern *** involved in operating,service,nuclear cleaning,chemical analysis,health physics,technical support,among others were randomly selected as the research targets,and 69 urine samples of no less than 50 mL were *** oxidative distillation method was used to pretreat the urine samples,and the activity concentration of tritium in distillate was then measured using liquid scintillation *** formula for the committed effective dose was also applied used to estimate the internal ***:The highest tritium activity concentrations in urine samples from three NPPs were 2412.7,6351.4,and 478.7 Bq/L,***,the internal doses due to tritium intake were 1.8,4.8 and 0.4μSv,***:The urine tritium activity concentration of workers varied greatly dependent on their job *** values for urine tritium radioactivity concentrations of workers involved in health care,nuclear cleaning and maintenance were generally higher than those for other job *** difference in urine tritium activity concentration mainly came from the different exposure time and tritium *** the dose assessment results,the internal dose caused by tritium intake did not exceed the public annual effective dose limit.

关键词： tritium Occupational exposure Urine Internal dose Nuclear power plant

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