Direct alpha spectrometry for characterising hot particle properties

Non-destructive analysis methods, especially direct alpha spectrometry but also gamma ray spectrometry and scanning electron microscopy were applied to a nuclear bomb particle from the Thule accident. The use of high-resolution direct alpha spectrometry with the aid of Monte Carlo simulations was demonstrated here in order to determine the properties of this particle. In general, the information that can be obtained through direct alpha spectrometry depends on the information available a priori. For example, known elemental composition makes the assessment of particle dimensions possible even if scanning electron microscopy images are unavailable. Although direct alpha spectrometry may be applied for particle characterisation, further developments in spectrum analysis tools are necessary.     

Self-irradiation induced structural changes in the transplutonium pyrochlores An2Zr2O7 (An=Am, Cf)

We have pursued the fundamental chemistry of actinide pyrochlore oxides, An₂Zr₂O₇ (An=Am, Cm, Bk, and Cf), using X-ray diffraction as well as optical spectroscopy. One recent facet of our studies has been to observe the structural changes of these materials under self-irradiation as a function of time. It has been reported that both titanate and silicate materials transform from a crystalline to an amorphous state under irradiation. With the Zr-based actinide pyrochlores studied here, we have observed a phase change from a pyrochlore structure to a fluorite-type structure with the retention of crystallinity. We focus here on the impact of α-radiation (²⁴³Am and ²⁴⁹Cf), rather than that from neutrons (²⁴⁸Cm) or β-radiation (²⁴⁹Bk), on the An₂Zr₂O₇ pyrochlore structures. As a result of this phase change, the local coordination environments of both the actinide and zirconium atoms are altered. We consider a defect/ion deficiency driven mechanism and also address the occurrence of oxidation of the trivalent actinides during the self-irradiation process as being potential mechanisms responsible for the observed phase change.     

Novel Template Sorbents for Separation of Americium(III) from Nitric Acid Solutions: Search of Optimal Ion‐Imitator of AmIII

A series of new template sorbents that enable selective and effective sorption of Am^III from 0.5 to 4M HNO₃ solutions containing high concentrations of Fe^III and Zr^IV was synthesized from (ethenyl)(diphenyl)phosphine oxide. La^III, Ce^III, and Pr^III were used as template elements imitating the properties of Am^III. The highest efficiency of separation of Am^III from high amounts of Fe^III and Zr^IV was displayed by the Ce^III‐based sorbent.     

Determination of Separated Plutonium,Americium and Curium in Environmental Samples by Sequential Extraction Techniques

A simple, reliable and practical radiochemical method for sequential isolation and determination of plutonium, americium and curium in a wide variety of environmental samples including soils, river sediments and water was developed. The isotopes determined are: ²³⁸Pu, ^239,240Pu, ²⁴¹Am, ²⁴²Cm and ²⁴⁴Cm. The methods involve leaching of soil or sedimental samples with concentrated nitric acid using a pressure digestion technique. Subsequent concentration and separation of nuclides of interest from major matrix elements and other interfering alpha-emitters are carried out by coprecipitation with ferric hydroxide and solvent extractions. Sources suitable for alpha-spectrometry are prepared by electrodeposition from acidic ammonium chloride solution. ²⁴²Pu and ²⁴³Am are used as tracer isotopes of plutonium and americium-curium elements, respectively. Some results of analysis of soils, sediments and water are given. The alpha peaks from ²³⁸Pu, ^239,240Pu and ²⁴²Pu as well as ²⁴¹Am, ²⁴⁴Cm, ²⁴²Cm and ²⁴³Am are well resolved. The entire analytical procedures for plutonium, americium and curium are completed in less than sixteen hours.     

双二苷酰胺从硝酸溶液中萃取Eu(Ⅲ)和Am(Ⅲ)

采用混合酸酐法合成了两种双二苷酰胺(bisdiglycolamide, BisDGA)萃取剂: N,N,N'',N''-四正辛基-N',N″-乙二基-双二苷酰胺(TOE-BisDGA)和N,N,N'',N''-四正辛基-N',N″-间苯二甲基-双二苷酰胺(TOX-BisDGA). 以磺化煤油和正辛醇混合溶液(体积比 90∶10)作稀释剂, 研究了它们在硝酸溶液中对Eu(Ⅲ)和Am(Ⅲ), 以及自身对HNO₃的萃取行为. 结果表明, 2种BisDGAs对HNO₃均有一定萃取, 当酸度不超过1.0 mol/L时, 二者形成1∶1型的萃合物. 随HNO₃浓度增加, Eu(Ⅲ)和Am(Ⅲ)的萃取分配比增加. 相同条件下, TOE-BisDGA对Eu(Ⅲ)和Am(Ⅲ)的萃取能力强于TOX-BisDGA. 斜率分析表明TOE-BisDGA和TOX-BisDGA与Eu(Ⅲ)和Am(Ⅲ)均形成2∶1型的萃合物. 温度升高, 萃取分配比下降, 萃取反应是放热反应. 2种BisDGAs对Eu(Ⅲ)的亲和力强于对Am(Ⅲ)的亲合力, 表明BisDGAs对Eu(Ⅲ)有一定的选择性. 同时, 研究了BisDGAs萃取Eu(Ⅲ)和Am(Ⅲ)的机理, 给出了表观萃取平衡常数和萃取反应热力学函数ΔH, ΔS和ΔG的值. 此外, 还对TOE-BisDGA和TOX-BisDGA与Eu(Ⅲ)形成的配合物进行了红外和紫外光谱分析.     

核燃料循环中镅的氧化分离研究进展

镅离子在溶液中主要以三价形式(Am(III))存在,因其离子半径与三价镧系离子Ln(III)接近,化学特性相似,使得Am(III)与Ln(III)的有效分离被认为是核燃料循环领域最具挑战性的课题之一。利用镅的多价态特性,采用不同氧化方法可将Am(III)氧化成高价态的AmO₂⁺和AmO₂²⁺形式,再通过溶剂萃取、沉淀等方法进行分离,是实现Am与Ln分离的一种新思路。本文综述了不同氧化方法对水溶液环境中Am(III)的氧化分离研究进展,描述了相关机理,指出了不同氧化方法的优劣并展望了未来发展趋势,以期为发展新型镧系与锕系元素分离技术提供参考。     

Extraction studies of Am(III) and Eu(III) with a tris-bipyridyl macrobicyclic ligand

Complexation of Am(III) with a tris-bipyridine cryptand (L) has been carried out in a nonaqueous medium (CH₃CN–CHCl₃). Subsequently the complexation behaviour was investigated using the reverse extraction tracer technique with dinonyl naphthalenesulphonic acid (HD) in toluene as the organic phase and varying concentration of HCl (upto 2M) as the aqueous phase. Equilibrium is attained in the two-phase system at a rate dependent on the hydrogen ion concentration in the aqueous phase. Whereas it takes only a few minutes to attain the equilibrium state at pH 6.0, a phase contact period of 50 days was insufficient if the acidity is greater than 0.4M, presumably due to the slow dissociation of the cryptate formed. The large enhancement in the distribution ratio value in the synergistic system with 1M HCl as the aqueous phase under non-equilibrium conditions is employed for the analytical separation of Am(III) from Eu(III).     

Contrôler et limiter la dispersion des produits radioactifs des centrales électronucléaires en cas d'accident

We examine the role of physical, chemical and physicochemical differences between the consequences of accidents occurring in high-risk technologies (oil extraction, refinery and transport, big chemistry process, space shuttle flying start, airplane, underground mining, high velocity train transportation, etc.) and the major radioactive major accidents in nuclear power plants (NPP) from the viewpoint of their sequels, confined or not confined, in space and time, and then, their serious impact on human societies, neighboring or not. We identify chemical (as volatile species, noble gases, etc.), physical bodies (as aerosols, etc.) containing radioactive nuclei released in these accidents and seek to control and reduce the causes of their diffusion in the atmosphere, migrations in soils and land, transfer in inland waters and oceans. We propose ways of scientific research leading to solutions with a view to get an improved control of these radioactive substances, and in particular:

• A.reducing as much as possible the irradiation duration by removing the fuel elements from the nuclear core of the NPP reactor and extracting all culprit radioactive nuclei;
• B.designing power reactors using liquid fuels that can be frequently or even continuously removed from the core of the reactor. The disputed radioactive substances can, then, be extracted by chemical processes. The purified nuclear fuel fluid may then be returned to the core;
• C.to separate, in a more radical manner, the circuits of the nuclear fuel and that of the cooling fluid, in order to decrease strongly the radioactive phenomena in the latter, easing its design, operation, maintenance and dismantling;
• D.using a fuel of lower atomic number than uranium or plutonium, as thorium. The use in the present-time fuel cycle of actinides with high atomic numbers Z (number of protons) and A (number of nucleons) leads, by successive neutron captures, to very high Z and A pair–pair nuclei (as americium and curium) subject to spontaneous fissions, then emitting neutrons of fission, even when the nuclear chain reaction is stopped. Neutron emissions are a major hazard if their mass production oversizes the laboratory level. It poses difficult, complicated scientific problems for human radioprotection. A way to improve concepts further than A, B, and C consists in using a nuclear fuel whose Z and A numbers are much smaller than those of uranium, for instance thorium. This is concept D studied here.

A substantial part of these lines of these four research routes has been already studied in other contexts, during the last half-century. What can be used is specified here, with the necessary extensions to the fields of physics, chemistry, and physical chemistry.     

吡啶吡唑基配体C8-BPP对硝酸溶液中Am3+和Eu3+的萃取

合成了吡啶吡唑基配体C8-BPP[2,6-bis（5-（n-octyl）-1H-pyrazol-3-yl）pyridine],并采用红外光谱、核磁共振波谱、质谱等手段对其进行了表征.以正十二烷为稀释剂,2-溴己酸为协萃剂,研究了C8-BPP从HNO₃溶液中萃取Am³⁺和Eu³⁺的行为.重点考察了萃取时间、酸度和萃取剂浓度等对分配比D和分离因子SF_Am/Eu的影响.在HNO₃浓度为0.2~1.0 mol/L时,C8-BPP萃取Am³⁺和Eu³⁺的D值随HNO₃浓度增加而减小,SF_Am/Eu值先增大后减小;HNO₃浓度为0.5 mol/L时,SF_Am/Eu达到55.随着配体浓度的增加,C8-BPP萃取Am³⁺和Eu³⁺的D值均增加,SF_Am/Eu值缓慢减小,但仍在40以上.斜率分析表明,C8-BPP萃取Am³⁺和Eu³⁺均形成了1： 1型的萃合物.还采用紫外滴定、高分辨质谱、红外光谱、拉曼光谱和时间分辨荧光光谱等方法研究了C8-BPP与Eu³⁺的配位化学行为,并得到了配合物的组成和稳定常数.