辐射交联低烟无卤阻燃热收缩电缆附件的研制

研究了辐射交联低烟无卤阻燃收缩电缆附件中的低烟无卤阻燃绝缘管、护套管和分指套等的配方,及其产品辐照加工工艺。电缆附件材料烟密度性能符合ＡＳＴＭＥ６６２,卤化氢一性能符合ＩＥＣ７５４－１,综合性能达ＤＬ４１３－９１“３５ｋＶ及以下电力电缆热收缩型附件应用条件”,电缆附件性能达ＧＢ１１０３３－８９“额定电压２６／３５ｋＶ及以下电力电缆附件基本技术要求”。     

TAIC对辐照交联无卤阻燃EVA热缩材料的影响

向乙烯-醋酸乙烯共聚物(Ethylene-vinyl acetate copolymer,EVA)无卤阻燃热缩材料中添加不同含量的三烯丙基异氰脲酸酯(Triallyl isocyanurate,TAIC),然后采用电子束辐照,制备出交联型无卤阻燃EVA热缩材料。考察TAIC的含量和吸收剂量对样品的凝胶含量、机械性能和电性能的影响,并通过傅里叶红外(Fourier transform infrared,FTIR)光谱对EVA热缩材料进行表征。结果表明:TAIC的加入对辐射交联有促进作用,在吸收剂量一定的情况下,如150 k Gy,EVA热缩材料的凝胶含量随着TAIC含量增加;在TAIC的添加量一定的情况下,如3份(质量),EVA热缩材料的凝胶含量随着吸收剂量增加;对机械性能而言,断裂伸长率随着TAIC和吸收剂量的增加均呈下降趋势;在断裂强度方面,添加TAIC的样品断裂强度上升趋势比较明显;对电性能的影响,TAIC的加入增加了EVA热缩材料的体积电阻,其随着吸收剂量的增加先上升后下低;FTIR分析表明TAIC在电子束辐照下反应完全。     

辐射制备POE/EPDM/SR/MH无卤阻燃绝缘材料的研究

使用电子加速器辐照制备了由聚烯烃弹性体(POE)、三元乙丙橡胶(EPDM)、硅橡胶(Siliconrubber)和氢氧化镁混炼而成的无卤阻燃绝缘材料,研究了配方对共混体系力学性能、阻燃性能、电性能等的影响。探索了力学性能与吸收剂量之间的相关性,研究了含硅体系与含硅磷体系各自的阻燃机理。发现拉伸强度与凝胶含量无直接对应关系,屈服强度与凝胶含量在一定剂量范围内有良好的对应关系;硅橡胶的加入可促进体系成炭,硅橡胶与红磷有协同阻燃作用。     

辐射交联无卤阻燃电缆材料的研究

经过选择树脂体系的比例,阻燃剂、抗氧剂、偶联剂和辐射交联剂的用量,加工制得辐射交联无卤阻燃电缆材料,其各项指标均满足“九五”重点科技攻关项目即辐射交联电线电缆新材料研究及产品开发的指标要求。同时,进行了材料的流变学性能研究。材料的氧指数为４０,抗张强度为１１．５ＭＰａ,断裂伸长率为３７０％。     

辐射交联无卤阻燃聚烯烃复合材料的研究

研究了ＰＥ、ＥＶＡ、ＥＰＤＭ、ＥＥＡ和它们共混物的辐射交联，选用三水合氢氧化铝和红磷作阻燃剂制备辐射交联无卤阻燃聚烯烃复合材料。实验结果表明，辐射交联不仅可改善材料的力学性能，而且可克服熔滴现象，提高氧指数，是一种有效的阻燃新技术。所获材料的氧指数为３１，抗张强度９．９ＭＰａ，断裂伸长率为２００％，可在电线电缆工业中推广应用。     

γ辐照二茂铁酰腙配位聚合物的介电性能研究

合成了三种二茂铁二甲酰腙金属(Cu、Co、Ni)配位聚合物,(PZM),研究了大剂量60Co γ辐照对配位聚合物的微波介电性能及温度-介电性能的关系,结果表明,随辐照剂量的增加及配位金属Cu、Co、Ni的顺序,配位聚合物的介电参数(ε',tgδ)增加,但其升温-降温为不可逆曲线.另外,用红外差谱及电镜(SEM)探讨了辐照前后配位聚合物的微波化学结构变化及形貌.研究表明,这类配位聚合物有可能发展成有潜在微波通信应用的光、电、磁性多功能高分子材料.     

核电站电缆选择要点技术

安全级电缆对核电站的安全运行和安全停堆起着十分重要的作用,核电站用的电缆一般具有以下特殊性能,如长期工作寿命、耐辐射、耐潮湿、低烟、无卤、阻燃等要求,因而对所采用电缆绝缘和护套材料以及试验都提出了很高的要求,本文针对核电站电缆选择时的一些要点进行了探讨。     

射线作用下聚合物部件寿命的预测

【英国《原子》1992年2月号第7页报道】聚合物由于分子结构的原因,容易被电离辐射损伤。聚合物材料的机械性质和电学性质,可被γ射线或电子束辐照显著地改变。聚合物部件在核工业中的应用很广。在这些应用中,聚合物部件可能会遭受到范围     

辐射交联聚合物的结晶动力学(英文)

电离辐射在工业上应用的基础是聚合物的辐射交联,它们是绝缘电线和电缆的交联,热收缩性材料的生产,泡沫塑料等等。辐射引发交联已经被广泛地研究,特别是凝胶的形成和聚合物结构、辐照条件对交联度的影响。对于一般法和辐射法交联的聚合物却很少有人研究它的结晶过程。例如,已经证明除了在非常高的吸收剂量外,辐照的聚乙烯中总的结晶度不受影响,但对于聚丙烯和聚丁烯在凝胶点剂量时,它们的结晶度大大减少。辐照聚合物的重新熔融,进一步减少了总结晶度。 本工作表明不仅总的结晶度而且结晶动力学也受辐射引发交联的影响。结晶速率指出结晶划分成二种不同增长机理的过程。冷却速率是一个重要的因素,它决定结晶过程并影响与交联的半晶聚合物的结晶度和形态有关的其它性质。     

高通量工程试验堆辐照试验能力和辐照试验技术

高通量工程试验堆(HFETR)作为我国在役运行功率最高的研究堆,是我国进行各种反应堆燃料和材料辐照性能研究的重要工具和平台。HFETR以动力堆燃料和材料的辐照研究为主,同时兼顾同位素生产等其他任务。HFETR辐照试验能力与其结构相关,包含静态容器辐照试验、仪表化辐照试验和回路辐照试验三种辐照试验形式。HFETR具有与各种辐照试验匹配的成熟的和应用经验丰富的辐照装置设计、辐照参数控制以及复合辐照环境控制等辐照试验技术。大量的材料和燃料辐照试验结果表明,HFETR现有的辐照试验技术能够完全实现受试件的辐照指标要求,并同时确保辐照试验开展以及反应堆运行的安全。     

Study on environmental effect on fatigue and creep-fatigue strength of 316FR stainless steel in sodium at elevated temperature

Low-carbon 316 stainless steel with medium-nitrogen (316FR) is considered as the principal structural material for next generation fast breeder reactor (FBR) plants in Japan. The material strength standard and the creep-fatigue life evaluation method for 316FR have been developed. However, they are based on the results of material tests in air, while actual structural material will be used mainly in liquid sodium environment in the plants. In order to clarify the environmental effect, cyclic bending tests were carried out with and without hold time in sodium. Tested materials were 316FR and conventional 304 and 316 stainless steels. Weld metal of 316FR was also tested. As a result, it was found that fatigue and creep-fatigue lives of 316FR in sodium were larger than those in air and no explicit consideration of the environmental effect is necessary in design. It was also found that the life evaluation method based on the ductility exhaustion concept is applicable to creep-fatigue life assessment in sodium.     

Commercialized fast reactor cycle systems and reactor core performance of the promising fast reactors

The Feasibility Study on Commercialized Fast Reactor (FR) Cycle Systems is under progress in order to propose prominent FR cycle systems that will respond to the diverse needs of society in the future. The design studies on various FR system concepts have been achieved and then the evaluations of potential to achieve the development targets have been also carried out. Crucial development issues have been found out for each FR system concept and their development plans for the key technologies are summarized as the roadmap. As a result, it has been confirmed that the sodium-cooled FR concept is highly suited to the development targets and R&D issues are related enhancing the economy with certain perspectives for realization. A flexible and robust development program for the FR cycle system will be proposed taking account of the characteristics for each FR concept until the end of the Phase II study.     

聚合物辐射交联热收缩材料研究进展

综述了可用于制备辐射交联热收缩材料的基础聚合物。例如，低密度聚乙烯(LDPE)、乙烯-醋酸乙烯共聚物(EVA)、乙烯-丙烯酸乙酯共聚物(EEA)、三元乙丙橡胶(EPDM)及共混聚合物，低密度聚乙烯-乙烯．醋酸乙烯乙酸酯共聚物(LDPE／EVA)、低密度聚乙烯-三元乙丙橡胶(LDPE／EPDM)、乙烯-醋酸乙烯乙酸酯共聚物-聚二甲基乙烯基硅氧烷(EVA／PDMVS)等及含有助剂的多相体系共混物的辐射交联基本规律，交联后产物基本结构和主要性能的变化。介绍了聚合物辐射交联热收缩材料研究方面的新进展，概述了该材料的应用领域，同时，对热收缩材料的研究和开发前景做了展望。     

辐射化学在功能型有机材料研制中的应用

Although radiation-chemical reactions have been applied to many industrial fields, especially to polymer industries, they are mainly aimed at improving mechanical, thermal and surface properties of the materials. Application of radiation chemical reactions to the construction of functional organic materials, such as electronic and optical materials, is relatively few. However, radiation-chemical reactions have the following characteristics that are advantageous for studying and constructing functional organic materials.     

惯性约束聚变靶材料掺杂技术综述

文章概要综述了惯性约束聚变掺杂靶材料的制备方法，内容包括聚苯乙烯掺卤素和过渡金属元素，玻璃与塑料掺簇粒子，以及塑料涂层掺高Ｚ金属等。简述了掺杂材料的分析测试手段及其在ＩＣＦ中的应用。     

Core characteristics of fast reactor cycle with simple dry pyrochemical processing

Fast reactor core concept and core nuclear characteristics are studied for the application of the simple dry pyrochemical processing for fast reactor mixed oxide spent fuels, that is, the Compound Process Fuel Cycle, large FR core with half of loaded fuels are recycled by the simple dry pyrochemical processing. Results of the core nuclear analyses show that it is possible to recycle FR spent fuel once and to have 1.01 of breeding ratio without radial blanket region. The comparison is made among three kinds of recycle fuels, LWR UO₂ spent fuel, LWR MOX spent fuel, and FR spent fuel. The recycle fuels reach an equilibrium state after recycles regardless of their starting heavy metal compositions, and the recycled FR fuel has the lowest radio-activity and the same level of heat generation among the recycle fuels. Therefore, the compound process fuel cycle has flexibility to recycle both LWR spent fuel and FR spent fuel. The concept has a possibility of enhancement of nuclear non-proliferation and process simplification of fuel cycle.     

Design and setup of a testing device to investigate a reduced sized attachment system mock up for the ITER EU HCPB-TBM under different mechanical loading conditions

In order to determine the forces acting on the EU-Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) during operation, a measurement system is developed. Therefore, two force reconstruction (FR) methods using measured strain signals are selected that are suitable for the application to the TBM. The first one, the augmented Kalman filter is a combined deterministic-stochastic approach. A second FR method based on the concept of a model predictive controller is proposed in this paper, which uses an optimization algorithm. In order to test the selected methods a testing device has been built which can be used to apply different force excitations on a reduced sized TBM mock up and measure the resulting strain signals of 16 strain gages. A simple tube mock up has been designed and manufactured to test and calibrate the FR algorithms. In addition, a second TBM mock up with attachment system is described. Finally, first results of the FR of a worst-case test case from simulated strain data of the simple tube mock up are presented.     

席夫碱型阳离子共价有机聚合物对99TcO-4化学替代物ReO-4的高效吸附分离

高锝酸根（TcO^-₄）的裂变产额高、环境迁移能力强、半衰期长,高效分离去除TcO^-₄在放射性环境治理和乏燃料后处理过程中具有重要意义。然而目前只有少数材料可以从水溶液体系中吸附TcO^-₄,研发动力学快和耐酸性的吸附材料仍然具有挑战。为此,通过席夫碱反应合成了两种阳离子共价有机聚合物材料（BPA-TAB-Cl和BPA-TAE-Cl）吸附ReO^-₄（TcO^-₄的非放射性类似物）。两种材料均具有超快的吸附动力学,几乎可以定量地在20 s内去除溶液中的ReO^-₄。即使在pH=2溶液中,材料的吸附能力也没有受到明显影响。在溶液中NO^-₃浓度超过ReO^-₄浓度100倍的情况下,两种材料也可以分别去除84%和79%的ReO^-₄,显示出优异的吸附选择性。在四次吸附-解吸循环之后,两种材料的吸附能力几乎没有变化。最后,吸附机理证实阴离子交换后两种材料中均存在ReO^-₄。结果表明,利用共价有机聚合物去除放射性污染物具有广阔前景。     

Main R&D issues for fast reactor structural design standard

For realization of economical and reliable fast reactor (FR) plants, the Japan Atomic Energy Agency (JAEA) and the Japan Atomic Power Company (JAPC) are cooperating on the “Feasibility Study on Commercialized FR Cycle Systems”. To certify the design concepts through evaluation of the structural integrity of FR plants, the research and development of the “Elevated Temperature Structural Design Guide for Commercialized Fast Reactor (FDS)” is recognized as an essential theme. The FDS focuses on particular failure modes of FRs such as ratchet deformation and creep-fatigue damage due to cyclic thermal loads. For precise evaluation of these modes, the research and development for three main issues is in progress. First, the “Refinement of Failure Criteria” needs to be addressed for particular failure modes of FRs. Secondly, the development of “Guidelines for Inelastic Design Analysis” is conducted to predict elastic plastic and creep deformation under elevated temperature conditions. Lastly, efforts are being made toward preparing “Guidelines for Thermal Load Modeling” for the design of FR components where thermal loads are dominant.