15MnTi钢的中子辐照效应

介绍了１５ＭｎＴｉ钢的母材，焊缝及其热影响区在不同注量的快中子辐照后，材料的机械性能变化的情况，根据试验结果表明，辐照温度为５０℃，快中子注量在１．０×１０＾１８ｃｍ＾－２到６．０×１０＾１８ｃｍ＾－２之间，１５ＭｎＴｉ钢的脆性转变温度增量△Ｔｃｖ与积分快中子注量的经验关系公式。     

HFETR辐照孔道中子特性研究

采用蒙特卡洛(MCNP)程序对辐照孔道中子特性进行研究,包括各辐照孔道E1.0 Me V时的中子注量率(φE1.0 Me Vf(29))与E0.625 e V时的中子注量率(φE0.625 e Vf(29))的比值k,辐照孔道阳面、阴面样品中子注量率比值,辐照孔道样品最佳布置高度。研究结果表明:高通量工程试验堆(HFETR)辐照孔道k值随轴向和径向变化不同,但平均变化程度一致;9#孔道阳面、阴面材料快中子注量率比值达1.43,而G7、K11孔道阳面、阴面材料快中子注量率比值相对较小,分别为1.21和1.18。综合考虑,对于P15孔道,辐照试验段样品布置区的高度可达500 mm;对于9#孔道,样品布置高度可适当增至600 mm。     

纳米晶Al的快中子辐照效应研究

采用真空热压技术将自悬浮定向流法制得的纳米Al粉压制成平均晶粒尺寸约为120nm的块体,并对其进行了注量为1.9×1012~7.2×1014 cm-2的快中子(E1 MeV)辐照。通过X射线衍射(XRD)分析、扫描电子显微镜与能谱(SEM-EDS)分析和显微硬度测试研究了快中子辐照对纳米晶Al的微观结构和显微硬度的影响。研究结果表明:快中子辐照同时造成了纳米晶Al的平均晶粒尺寸增大和显微硬度提高。随快中子辐照注量的增大,纳米晶Al的平均晶粒尺寸和显微硬度分别增大了2.09%~9.09%和3.54%~4.37%。纳米晶Al的平均晶粒尺寸的增长率随快中子注量的增加而增大。     

Magnetic Properties of Uranium Carbides after Neutron Irradiation

Fundamental investigations on valence control and solvent extraction of americium were carried out to develop a method for americium separation from reprocessing solution. In order to adjust americium valency from III to IV and VI, (NH₄)₁₀P₂W ₁₇O₆₁ synthesized was used as complexant stabilizing Am(IV). Oxidation behavior of americium was investigated as a function of (NH₄)₁₀P₂W ₁₇O₆₁ americium ratio. Using 0.1M (NH₄)₂S₂O₈ and 0.01M AgNO₃ as oxidation reagent, Am(IV) was obtained quantitatively at the ratio of 15. On decreasing the ratio to 0.6, 92% of americium was adjusted to Am(VI). The concentration of (NH₄)₂S₂O₈ could be reduced to 1/15 compared to the previously reported method in which no complexant was used. Americium(IV) was also prepared by reacting O₃ and AgNO₃ but no Am(VI) was obtained even at low (NH₄)₁₀P₂W ₁₇O₆₁ to americium ratio.

Americium(VI) could be extracted by tri-n-butyl phosphate stably without influence of (NH₄)₁₀P₂W ₁₇O₆₁. The distribution coefficient of Am(VI) was 4 between 100% tri-n-butyl phosphate and 1 M nitric acid, and separation factor from Nd(III) was 50.

With regard to the americium separation method which implemented valence control followed by extraction, adding (NH₄)₁₀P₂W ₁₇O₆₁ led to minimization of waste volume and improvement of extraction efficiency.     

采用国产Am-Be中子源进行热中子活化的样品照射位置选择

利用热中子活化样品,合适的照射位置是取得良好活化效果的关键.经过MCNP模拟和实验测量,给出了采用国产Am-Be中子源进行热中子活化的样品照射位置的合理范围.     

Thick Lithium Metal Target for Fast Neutron Production

A high flux fast neutron was produced by the (d, n) reaction of a lithium metal target. A thick lithium layer for the target was prepared by a simple method of melt-coating on a copper plate. The fast neutron (>9 MeV) flux at a distance of 6mm from the target was (9.0±1.6)×l0⁶ n/cm²·sec·μA with use of a 2.0 MeV deuteron beam. A flux of 2.7×10⁹ n/cm²·sec was obtained by bombarding the target with the deuteron beam of 300 μA.     

DLC薄膜中子辐照效应

采用射频等离子体化学汽相沉积法得到了类金刚石（以下简称DLC）薄膜,并用能量为14MeV的中子对其进行辐照,辐照剂量为1.4×1012n/cm2～7.2×1012n/cm2。通过Raman及红外光谱分析得出,中子辐照造成膜中SP3C-C键的明显减少及SP2C=C键的增加,并形成少见的非晶型SP1C≡C键碳（直线型碳）,使DLC膜进一步非晶化。经辐照后的DLC薄膜红外透过率均有所提高,在实验剂量范围内,基本上与辐照剂量无关。     

Effect of Neutron Irradiation on Deformation Behavior of Zirconium

The effect of neutron irradiation on the tensile deformation behavior of zirconium was examined at room temperature at various strain rates ranging of 2.2×10^?4~2.2× 10^?2 sec^?1. The microstructure of the deformed specimens was observed by transmission electron microscopy. It was established that neutron irradiation diminishes the uniform elongation and the strain hardening rate, and hastens the onset of plastic instability. These phenomena are attributed to inhomogeneous deformation in the dislocation channels in the irradiated and deformed zirconium.

From the relation between strain rate and tensile properties (yield stress, ultimate tensile stress, uniform elongation and strain hardening rate), it was established that in unirradiated zirconium deformation is controlled by slip at strain rates below 6×10^?3 sec^?1, while above this threshold, twinning as well as slip contribute to deformation.

Neutron irradiation markedly inhibits deformation twinning in zirconium at room temperature. At 77 K, on the other hand, deformation by twinning is more prominent in irradiated specimens. The mechanism of twinning inhibition due to neutron irradiation is discussed.     

商用三端稳压器的中子辐射效应

实验研究了两种型号(CJ79L05011和CJ7905011)的商用三端稳压器在不同负载情况下中子辐射效应,得到了输出电压随中子注量的变化曲线。借助三端稳压器的简化模型,分析认为中子辐射下晶体管放大倍数的减少是造成三端稳压器输出电压变化的关键因素,并理论推导了输出电压和晶体管放大倍数的关系,利用PSPICE软件进行了模拟仿真,结果表明理论曲线和实验现象是基本一致的。     

SPRR-300反应堆辐照孔道中子注量率的MCNP程序计算

利用MCNP程序的重复几何结构功能,对SPRR-300的堆芯几何结构进行了简化处理,建立了该堆辐照孔道中子注量率分布计算的数学模型.计算值与实验值的比较结果表明,二者符合很好,验证了本文建立的数学模型的合理性和可行性.     

Low Temperature Neutron Irradiation Test for X21 Steel

正Low temperature neutron irradiation test on base and weld metal of X21 steel were carried out at 49-2 swimming pool test reactor in CIAE.Then tensile and impact properties were test on the before and post irradiation specimens.And then irradiation hardening and embrittlement were analyzed according to the test result.     

中子辐照法在炸药来源认证中的应用

核弹头的拆卸认证是核裁军和军控核查中的一项重要研究内容。核弹头拆卸后,核查方将对拆卸出的特殊核材料和高爆炸药进行探测和认证,确保两者来源于核弹头。本文着重研究铀弹头（基于武器级铀的核弹头）内部拆卸出的炸药的认证方法,提出基于中子辐照法的炸药认证方案,并建立基于Geant4软件的数值模拟计算平台,利用该平台对该方案的可行性和效果进行模拟计算研究。研究结果表明,核查方应单方面设定辐照时间,设置适当的核弹头拆卸时间,并探测拆卸出的炸药中¹³N和¹¹C核素的β⁺衰变,即可区分真实铀弹头中拆卸出的炸药和炸药赝品,进而为判断炸药是否来源于铀弹头提供重要依据。     

Effect of Neutron Irradiation on Mechanical Properties of Al-Li Alloys

An increase in yield stress at room temperature was observed in Al-0.6W/0 Li alloy irradiated to thermal neutron doses of 2.9 × 10¹⁹ to 7.2 × 10¹⁹ cm^?2. The hardening of as-irradiated specimens is accompanied with yield point followed by jerky yield-elongation in the stress-strain curve. The radiation hardening could not be annealed out by heating for 30 min at temperatures up to 350°C, whereas the yield-elongation disappeared gradually with increasing heating temperature in the l mm diam. specimens; with the 2 mm diam. specimens the yield-elongation still remained even after post-irradiation heating for 30 min at 350°C. Strengthening accompanied by jerky yield-elongation is considered to be due to He atom clusters precipitated along the dislocation. The hardening observed in the specimens heat-treated after irradiation at temperatures above 250°C is caused by randomly distributed gas bubbles.

In heavily cold-worked Al-0.6%W/o Li specimens, recovery of work hardening occurred during neutron irradiation to 4.2 × 10¹⁹ cm^?2. Hardening due to gas bubbles was also observed in the cold-worked specimens. In Al-2.7W/0 Li alloy, an increase in yield stress took place in the specimens irradiated to 4.2 × 10¹⁹ cm^?2 and heated for 30 min at temperatures of 155° to 260°C. The hardening is thought to be due to re-precipitation of β-phase resolved during the neutron irradiation.     

Grain Growth and Neutron Irradiation Effect in Al-Li Alloys

The analytical solution of the isotropic, one-dimensional and time-dependent transport equation is expressed by the superposition of a newly defined Green function of the virgin neutron flow. As a result, the solution of the neutron transport equation is given by the superposition of beams possessing wave fronts. The present study has introduced the possibility of clearly explaining neutron transport behavior by beam processes, thus providing a further insight into the interpretation of the transport equation. This method should prove useful when the continuous mode is superior to discrete modes. The solution for the stationary case is also derived.