裂变中子

~（235）U裂变中子谱的平均（n，p）反应截面的系统研究

Systematics of the ( n , p ) Reaction Cress Sections Averaged over ￣( 235 ) U Thermal Fission Neutron Spectrum

研制了狭缝外延式高灵敏大面积PIN裂变中子探测系统。

A fission neutron detector system with frontward_extended lead slot collimator has been developed and tested .

GM计数管对裂变中子的相对灵敏度

The Relative Sensitivity of GM Counter to the Fission Neutrons

用~（252）Cf自发裂变中子源刻度中子探测器效率

Efficiency calibration of neutron detectors with ￣( 252 ) cf spontaneous fission neutrons

一种~（252）Cf裂变中子源的中子、γ射线飞行时间谱测量新方法

TOF spectrum measurement of ~ ( 252 ) Cf source fission neutron and gamma ray

基于~（252）Cf裂变中子源的核信息系统频谱分析

Spectrum analysis of nuclear information system based on ~ ( 252 ) Cf fission neutron source

n-γ分辨应用于~（252）Cf自发裂变中子飞行时间谱测量

The application of n - γ discrimination in ~ ( 252 ) Cf spontaneous neutron TOF spectra measurement

~（252）Cf裂变中子源在组织等效模体中的中子和γ辐射剂量分布的计算

Calculation of dose distribution for ~ ( 252 ) Cf fission neutron source in tissue equivalent phantoms using Monte Carlo method

~（252）Cf自发裂变中子源的化学回收流程

Chemical process for the recovery of ~ ( 252 ) CF from a ~ ( 252 ) CF spontaneous fission neutron source

~（252）Cf自发裂变中子诱发~（235）U裂变时几个核素裂变产额的绝对测定

The absolute determination of cumulative yield of several nuclides from induced fission of ~ ( 235 ) u by neutrons of spontaneous fission of ~ ( 252 ) cf

脾细胞IL－2产生能力对裂变中子和γ线的辐射反应相近，D＿（37）均约为2.5Gy，裂变中子RBE为1。

The responses of splenic IL-2 production to fission neutron and gamma-ray irradiation were similar : bothD_ ( 37 ) values being about 2.5 Gy .

用MCNP程序计算核燃料废包壳缓发裂变中子形成的热中子通量密度

Computing with MCNP the thermal flux density due to the delayed fission neutron generated in processing the clads of burned-up fuel roads

由于铀，钍、锕三系能直接发射微量重离子~（14）C，以及自发裂变中子和α-衰变与物质发生核相互作用，也可产生~（14）C。

Heavy-ion 14 ~ C can not only be directly emitted by three radioactive series ( 238 ~ U , 235 ~ U and 232 ~ Th ), but can also be produced by neutrons of the spontaneous fission and α - decay interacting with matter .

采用MCNP程序计算了狭缝式裂变中子探测器的结构设计和磁场对n/γ分辨能力的影响。

The influence of configuration designs and magnetic field on n / γ discrimination for the slot-calibrated PIN fission chamber detector system was calculated by using MCNP code .

目的：以60Coγ射线为参比射线，研究裂变中子诱导小鼠胸腺细胞凋亡的时间效应，并初步探讨其分子机制。

Objective : To study the time response of fission neutrons induced apoptosis in murine thymocytes with 60 Co γ - rays as the reference radiation and to investigate preliminarily its molecular mechanism .

结论对于裂变中子照射，在事故后利用头顶部位测量到的24Naγ初始计数率及Bm值可在几小时内估算出个人受照射的中子注量和剂量。

Conclusions Following an accident , the original counting rate of 24 Na γ at the top of head and B m , value of an individual receiving neutron fluences and neutron dose from nuclear fission can be used to estimate neutrons within a few hours .

裂变中子（252Cf）对裂变链（235U系统）的依存关系，它是各种频域和时域测量核信息系统反应性的基础。

The dependency relation of fission neutron ( 252Cf ) - fission chain ( 235U system ) is the foundation for reactivity measurement of nuclear information systems in frequency domain and time domain .

组件燃耗对堆芯裂变中子源参数的影响

Impact of Fuel Assemblies Burn-Up on Core Fission Neutron Source Parameter

关于裂变中子谱结构现象的理论探讨

Some theoretical investigation for the structure phenomenon of fission neutron spectra

脉冲裂变中子总数测量新方法的理论研究

Theoretical research of a new measurement method of pulse fission neutrons

狭缝式高灵敏裂变中子探测系统

A high sensitive fission neutron detector system with a lead slot collimator

裂变中子照射后小鼠小肠上皮的损伤和修复

The damage and repair of the intestinal epithelium in neutron - irradiated mice

裂变中子和γ射线照射小鼠骨髓增殖能力的比较

Comparison of proliferation ability of bone marrow in fission neutron and y-ray irradiated mice

次模拟裂变中子源能谱测量

Energy spectrum measurement of Sub-mock fission neutron sources

狭缝式裂变中子探测系统伽玛辐射灵敏度实验研究

Experimental study of the γ sensitivity of the slot-collimated PIN fission neutron detecting system

用阈探测器测量热中子引起的U~（235）裂变中子能谱

Measurement of thermal - neutron - induced ( 235 ) ~ u fission spectrum by threshold detectors

塑料闪烁探测器因其具有对辐射粒子探测效率高、发光效率高、以及时间响应较快等优点，因此在脉冲辐射测量，尤其在脉冲裂变中子的测量中得到了广泛的应用。

Development of Scintillator-photomultiplier Neutron Detector Plastic scintillation detectors are widely used in measurement of pulse fission neutron and r radiation .

因此，在中子输运计算中，必须考虑组件燃耗对堆芯的裂变中子源参数的影响。

So the impact of fuel assemblies burn-up on core fission neutron source parameters shall be considered in the neutron transportation calculation .

在中子输运计算中，准确的裂变中子源是保证计算结果可靠性的前提和基础。

For the neutron transportation calculation , accurate fission neutron source is the prerequisite and fundament ensuring that the calculation results are reliable .

局部屏蔽对裂变中子照射狗的防护作用&Ⅲ.屏蔽材料厚度和综合治疗措施对防护效果的影响

The protective effects of partial shielding on FISSION-NEUTRON irradiated dogs ⅲ . the influence of the thickness of the shielding materials and therapeutic procedure upon the protective effects