| 1. | Standard field procedures are employed in taking samples for analysis by delayed neutron determinations .
采用标准的实际操作规程为缓发中子测定分析取样。 |
| 2. | Long period delayed neutron
长半衰期缓发中子 |
| 3. | Uranium analysis by the emission of delayed neutrons , following fission of u235 , has been described by amiel
阿密尔论述了应用u235裂变后产生的缓发中子流分析铀的方法。 |
| 4. | The sutdy on technique of measuring fission , delayed neutrons from uranium materials and the method of distinguished nuclear from non nuclear materials with the active method are described
用主动方法研究了核材料铀的裂变缓发中子测量技术和区分核与非核材料的方法。 |
| 5. | If using the natural uranium to replace the heu pit in warhead , the delayed neutron counting rate would be about 3 times lower . the coincidence neutron detection is proposed to be used in nuclear warhead detection
计算表明用天然铀替代高浓铀作的假弹头，它们的出壳缓发中子数相差约3倍，需在一定条件下，才可对真伪核弹头做出判断。 |
| 6. | Detecting nuclear warhead by counting delayed neutrons induced by neutron source is studied . the 2 - step calculation method is proposed to resolve the delayed neutron transportation issue . this method can save computer ' s calculation time , and is easy to operate
本文研究了用外中子源照射核弹头，诱发其裂变材料裂变，探测缓发中子的方法，以此判断高浓铀与低浓铀，从而为核查核弹头的真伪提供依据。 |
| 7. | A mathematic model of reactor , steam generator , pressurizer is developed based on characteristic of pwr coolant system . for reactor , the point reactor kinetics equation with six - group delayed neutrons is used and influence of coolant ' s and fuel ' s temperature is considered , conduction model of one dimension and single - channel model is used in thermal and hydraulic calculation , third - order hermite polynomial is used to solve the point reactor kinetics equation
对于反应堆，在物理计算中采用了带有六组缓发中子的点堆方程，同时考虑了多普勒效应及冷却剂温度效应对反应性的影响；在热工水力计算中采用了一维的热传导模型与单通道模型；在求解点堆方程中采用了hermite插值的方法，克服了点堆方程的刚性问题。 |
