辐照三烷基氧化膦萃取锶和铯的研究

研究了γ辐照后的３０％％ＲＰＯ－煤油－ＨＮＯ３体系萃取Ｓr和Ｃs的性能。利用ＩＣＰ－ＡＥＳ及ＡＡＳ分别测定两相中Ｓr和Ｃs浓度，分配比。试验了辐照剂量对分配比的影响。结果表明，γ射线辐照对ＴＲＰＯ的萃取笥能无显著影响。     

三烷基氧膦（TRPO）辐射稳定性研究：辐解损失率的测定

三烷基氧膦是用于高放废液处理的萃取剂,本文试验了在辐照剂量为１×１０＾４Ｇｙ－１×１０＾６Ｇｙ时ＴＲＰＯ损失率。结果表明,１００％（Ｖ／Ｖ）ＴＲＰＯ在λ辐照剂量１０＾４Ｇｙ－１０＾６Ｇｙ变化时,辐解损失率为１．２％－１．６％;３０％（Ｖ／Ｖ）ＴＲＰＯ－煤油在辐照剂量１０＾４Ｇｙ－１０＾５Ｇｙ时,辐解损失率基本不变（０．３３％－０．３４％）,而在１×１０＾６Ｇｙ时增加到０．７７％。均低于磷酸三丁酯的     

三烷基氧化膦中醇羟基的分光光度研究

三烷基氧化膦是用于处理高效废液的萃取剂。显著量的醇的存在有可能影响它的萃取性能。本文研究采用分光光度测定法，测定辐照前后的ＴＲＰＯＫ醇羟基的含量结果表明，ＴＲＰＯ中只有少量醇，而辐照亦未导致醇羟基含量的显著增加。     

CW-COIL激光辐射锗-硫化铅探测器的实验研究

本文叙述了锗－硫化铅（Ｇｅ－ＰｂＳ）探测器的基本特性。分析了激光辐射锗滤光片使用材料升温的穿透深度随时间的变化。在光斑面积２．４６ｍｍ×３．６９ｍｍ和辐照时间０．８ｓ的条件下，得到连续氧碘激光（ＣＷ－ＣＯＩＬ）辐照锗滤光片的烧蚀阈值为１２４Ｗ和破裂阈值为１７７Ｗ的实验数据。在此基础上，进行了ＣＷ－ＣＯＩＬ辐照Ｇｅ－ＰｂＳ探测器的热效应研究，在光斑直径２．１ｍｍ和辐照时间０．８ｓ的条件下，给出ＣＷ－ＣＯＩＬ使Ｇｅ－ＰｂＳ探测器致盲的阈值为１７Ｗ、永久失效的阈值为１９８Ｗ的实验结果。研究结果表明：ＣＷ－ＣＯＩＬ辐照Ｇｅ－ＰｂＳ探测器的破坏机理是激光加热和热应力联合作用的结果。锗滤光片升温，造成硫化铅探测器环境温度升高，导致其探测灵敏度下降为零是ＣＷ－ＣＯＩＬ辐照Ｇｅ－ＰｂＳ探测器产生致盲的原因。激光辐照功率越高，Ｇｅ－ＰｂＳ探测器致盲、恢复时间就越长，甚至造成永久性的失效。     

D2EHPA萃取稀土的有机相红外光谱及添加DMHPA的影响

本文研究了部分皂化的二（２－乙基己基）磷酸（Ｄ２ＥＨＰＡ）－正庚烷体系萃取稀土离子Ｙ＾３＋，Ｐｒ＾３＋，Ｎｄ＾３＋，Ｅｕ＾３＋后有机的傅里叶变换红外光谱（ＦＴ－ＩＲ）。发现不同稀土离子与萃取剂的配位能力有差异，并且皂化度对萃取有机相中的Ｐ＝Ｏ谱带的频率和吸收强度皆有影响，在Ｄ２ＥＨＰＡ中加入二（１－甲基庚基）磷酸（ＤＭＨＰＡ）导致Ｐ＝Ｏ谱带形状和吸收强度发生变化。     

TOPO－TBP萃淋树脂在盐酸、硝酸溶液中萃取铀、钍平衡常数的测定

本文测定了在盐酸、硝酸溶液中，ＴＯＰＯ－ＴＢＰ萃淋树脂萃取铀、钍的平衡常数，结果表明，在相同酸性溶液中，ＴＯＰＯ－ＴＢＰ萃淋树脂萃取铀、钍平衡常数与液－液体系基本一致。     

辐照三烷基氧化膦在水相中溶解度的研究

三烷基氧化膦是镧系元素和锕系元素的高效萃取剂。本文用ＩＣＰ－ＡＥＳ法测定萃余水相中的磷,用以研究三烷基氧化膦在纯水、酸液及碱液中的溶解度。结果表明,随着γ射线辐照剂量的增加,三烷基氧化水膦在水相中溶解度增加,并且在碱液中有较高的溶解度,在纯水中有较低的溶解度。     

三烷基氧化膦辐解产物的气相色谱研究

用高分辨率毛细管气相色谱法及等离子体光谱法研究了核工业领域应用的萃取剂三烷基氧化膦（ＴＲＰＯ）酸性含磷解产物。研究表明,在γ辐照条件下酸性辐解产物主要为二烷基膦酸、一烷基膦酸,磷酸及脂肪酸。其产额分别为０．５８、０．６７、０．０１４及０．５６。     

PbWO4闪烁晶体的辐照损伤机理研究

完成了６４０—１０４０℃温度范围内钨酸铅［ＰｂＷＯ４（ＰＷＯ）］晶体的退火实验,观察到较低温退火时晶体中本征色心吸收带（３５０ｎｍ）先是增加,其后随退火温度的升高而逐渐降低直至消除的全过程．分析了ＰＷＯ晶体的本征缺陷和电荷补偿机制．讨论了退火过程中氧进入晶体后色心的产生和转化规律,并提出可能发生Ｐｂ３＋→Ｐｂ４＋的进一步氧化过程,从而导致Ｐｂ３＋空穴中心的湮没．测量并比较了不同退火温度处理后ＰＷＯ晶体的紫外辐照诱导色心吸收谱．观察到导致辐照损伤的Ｏ－空穴中心主要来自晶体中固有的Ｐｂ３＋空穴中心向Ｏ－空穴中心的转化;同时晶体中氧空位作为电子陷阱对Ｏ－空穴中心有稳定作用．当上述两项因素得以消除,晶体辐照硬度随之提高．实验表明,在含氧气氛中高温退火可以有效地改进ＰＷＯ晶体的抗辐照损伤能力．铁杂质对ＰＷＯ的抗辐照能力十分有害     

P538萃取锰（Ⅱ）的研究

在２５±０．５℃，用Ｐ５３８的环己烷溶液从ＮａＣｌＯ４－ＨＣｌＯ４介质中萃取Ｍｎ（Ⅱ）的反应机理为离子交换机理，萃取焓△Ｈ＝－１９６ｋＪ．ｍｏｌ＾－１并用Ｃｌ＾－离子水合作用和Ｍｎ＾２＋与Ｃｌ＾－形成配合物的竞争解释了萃取分配比与水相中ＮａＣｌ浓度的关系。     

三烷基氧膦成分的气相色谱研究

三烷基氧膦（ＴＲＰＯ）用于做放射性废液和化学分离过程的萃取剂。本文用气相色谱技术研究和测量其组成。气相色谱条件为：ＦＦＡＰ毛细管色谱柱；Ｎ２载气，氢火焰原子化检测器，结果表明，不同厂家生产的ＴＲＰＯ其组成不同，其纯度也不同。     

三烷基氧化膦及其萃合物的红外光谱研究

三烷基氧化膦是一种新型的镧系元素和锕系元素萃取剂，本文研究了其红外光谱特征及其与稀土元素和硝酸所形成的萃合物的红外光谱。     

Spectroscopic investigations on glasses,glass-ceramics and ceramics developed for nuclear waste immobilization

Highly radioactive nuclear waste must be immobilized in very durable matrices such as glasses, glass-ceramics and ceramics in order to avoid their dispersion in the biosphere during their radioactivity decay. In this paper, we present various examples of spectroscopic investigations (optical absorption, Raman, NMR, EPR) performed to study the local structure of different kinds of such matrices used or envisaged to immobilize different kinds of radioactive wastes. A particular attention has been paid on the incorporation and the structural role of rare earths—both as fission products and actinide surrogates—in silicate glasses and glass-ceramics. An example of structural study by EPR of a ceramic (hollandite) irradiated by electrons (to simulate the effect of the β-irradiation of radioactive cesium) is also presented.     

泡塑负载TRPO分离富集微量金

将三烷基氧化膦(TRPO)负载在泡沫塑料上制得了TRPO负载泡塑。以火焰原子吸收光谱法(FAAS)为检测手段,研究了负载泡塑对微量金的静态吸附性能。建立了负载TRPO泡塑分离富集-FAAS测定微量金的方法。方法精密度(RSD,n=10)在1.23%—8.22%之间,通过对标准物质的分析,测量值与标准值基本一致。     

热处理对氢气放电实验用靶的影响

对本底靶进行热处理后用TiT源重新开展打靶实验,未知谱线消失,证明未知谱线不是由靶中杂质造成的。将同种材料制成的两块本底靶分别进行热处理和不做任何处理,置于氢气放电源中进行照射生成源照靶,用TiT源打这两块源照靶发现照射前经热处理的靶产生的4条未知谱线较强,证明热处理能够增强靶吸附未知粒子的能力。     

Natural Transmutation of Actinides via the Fission Reaction in the Closed Thorium–Uranium–Plutonium Fuel Cycle

It is shown for a closed thorium–uranium–plutonium fuel cycle that, upon processing of one metric ton of irradiated fuel after each four-year campaign, the radioactive wastes contain ~54 kg of fission products, ~0.8 kg of thorium, ~0.10 kg of uranium isotopes, ~0.005 kg of plutonium isotopes, ~0.002 kg of neptunium, and “trace” amounts of americium and curium isotopes. This qualitatively simplifies the handling of high-level wastes in nuclear power engineering.     

The activation contamination in the metal-based ionization chambers as gamma dosimeters in the mixed filed dosimetry

This study aims to determine the activation contamination in the metal-based ionization chambers, i.e. Mg(Ar)- and Al(Ar)-chambers. The contamination was estimated by directly measuring the signal caused by the radioactive nuclides after the irradiation. The INAA gamma ray spectra clearly showed that the ionization chambers were activated. The activation contamination could comprise more than 2% of the total measured current of the Mg(Ar)-chamber, and more than 50% of the Al(Ar)-chamber, both irradiated free-in-air at the THOR epithermal neutron beam. The activation contamination provides concrete evidence of the necessity of the thermal neutron sensitivity correction.     

放射性束辐照生物学效应及相关生物物理机理

介绍了β缓发粒子衰变放射性束 9C辐照处于不同贯穿深度上人类唾液腺细胞的深度存活效应。 与稳定的 12C束流相比, 放射性 9C束流在其Bragg峰区附近展示了增强的生物学效应, 即细胞的致死效率明显增强。 探讨了放射性束 9C在其Bragg峰区展示增强生物学效应的生物物理机制, 并介绍了利用另一种放射性束 8B进行辐照生物学效应研究的新进展。 最后, 提出了一些利用放射性束可进行的辐照生物学效应前沿研究。 The depth survival effect of a β delayed particle decay 9C beam on human salivary gland (HSG) cells is presented in this paper. Compared with a stable 12C ion beam, the radioactive 9C ion beam showed an enhanced biological effect, i.e., remarkably enhanced efficiency in cell killing, at the penetration depths around its Bragg peak. The biophysical mechanisms underlying the enhanced biological effect are discussed herein, and the latest progress in biological effect induced by another radioactive 8B ion beam is introduced. In the end of this paper, several topics concerning the frontier of the radiation induced biological effects using radioactive ion beams are proposed.     

Calculation of production and decay of radioisotopes for future irradiation experiments and ion beam facilities

The design of future radioactive ion beam (RIB) facilites requires the forecast of radio isotope inventory after irradiation. At CERN – ISOLDE, we developed a software that estimates the activity of irradiated materials as a function of time dedicated to radioactive waste management. This tool can also be used for licensing procedures, planning of irradiation experiments and the estimation of yields.