托卡马克中聚变中子的能谱测量

大、中型托卡马克在D-D和D-T运行条件下聚变中子能谱测量具有重要意义。论述了几种最新的聚变中子能谱仪,评估了各种聚变中子能谱仪的优势、适用的范围和技术方面的局限性,并对即将建成的HL-2A(中国环流器二号A)托卡马克的聚变中子的泄漏能谱测量以及研究聚中子在通过中子倍增剂过程中的能谱变化,在聚变中子能谱诊断方面提供了几种可供选择的技术方案。     

14 MeV中子(n,p)反应截面的系统学研究

研究中等和重质量核１４ＭｅＶ（ｎ,ｐ）反应截面的系统学特性．在对实验数据进行分析、评价的基础上,给出了系统学经验公式,并计算了一批核素的反应截面,理论计算与实验结果符合较好     

14 MeV中子防护体设计的MCNP模拟

用富氢材料防护产额为108个/s的D T中子发生器, 当富氢材料厚度大于76 cm时, 其中子辐射剂量低于0.025 mSv/h. 为降低防护体厚度, 用铜和含硼聚乙烯组成的双层材料作为14 MeV中子防护体. Monte Carlo(MCNP)计算结果表明, 若中子辐射剂量小于0.025 mSv/h, 则双层材料的最小厚度为52 cm, 硼的质量分数为1.00%, 铜和含硼聚乙烯的厚度分别为37 cm和15 cm.     

剩余油饱和度的测井评价方法

 目前能够过套管测量剩余油饱和度的方法主要有过套管电阻率测井、碳氧比测井、中子寿命测井、中子伽马注钆测-渗-测、脉冲中子-中子测井（PNN）等。综述了套后剩余油饱和度的测井评价方法,分析了各种方法的测量原理、技术应用、适用性及实例,总结了目前应用较为广泛的剩余油饱和度测井评价方法。     

双热中子束流治疗孔道低浓化BNCT堆初步设计

以我国已经建成的高浓铀为燃料的BNCT堆为研究对象,将其堆芯低浓化并且添加水平热中子双束流治疗孔道,开展双热中子束流BNCT堆堆芯低浓化初步设计,计算分析该BNCT堆的keff、控制棒价值、顶铍效率、堆芯能谱、堆芯径向通量、轴向通量、辐照管通量等参数,得到双热中子束流治疗孔道低浓化BNCT堆初步设计方案.     

中子多重性数学模型分析及其推证研究

针对中子多重性分析计算方法中存在的问题展开研究,提出了样品铀和钚增殖因子M、样品诱发裂变率F、样品反应率与自发裂变中子发射率的比值α的优化计算方法。首先通过数学分析及推导得出了样品铀的M和F的计算公式,提出更为精确的计算方法;其次运用反证法证明了现有文献关于钚材料的M、F及α计算中存在的问题,订正其纰漏,提出了更容易实现的计算方法。该优化计算方法步骤简明、可操作性强,具有很强的实用价值。     

超子同位旋相互作用能对超子星转变密度的影响

利用相对论平均场理论, 考虑重子八重态{n,p,Λ,Σ^-,Σ⁰,Σ⁺,Ξ^-,Ξ⁰}, 研究了超子同位旋相互作用对超子星转变密度的影响. 结果表明: 考虑超子同位旋相互作用, 当x_ρΣ分别取2,1,2/3时, 超子星的转变密度逐渐降低; 当重子数密度取为超子星转变密度时, Λ和Ξ^-超子对超子星转变密度贡献最大, 二者之和约占总超子数的80％;  Ξ^-超子的数量随x_ρΣ的减小而降低,  Λ超子的数量分别占总超子数的34.2％,35.8％和33.8％.     

The design and calculation of the delayed neutron detection system for PWR and CEFR

This paper discussed the importance of the delayed neutron detection system. We improved the delayed neutron detection station and delayed neutron detector, so the noise was greatly decreased and the detection efficiency was greatly increased. After the improvement the stability of the detector was enhanced and the false alarm was eliminated. We introduced the principle of the gas lift pump designed for the sodium cooled fast reactor. A calculation model of the failed fuel detection system of CEFR was proposed, and from the model a code using LabWindows/CVI was developed. The minimum broken area that could be detected by the delayed neutron detection system of CEFR was calculated and the delayed neutron detection signal in a few representative transient conditions during fuel failure happened was stimulated.     

The review and prospect of neutron radiography in China

Neutron radiography is one of radiography non-destructive testing. It is a valuable complementary of X and γ rays radiography. The present status and history of neutron radiography in China was described briefly, facilities of neutron radiography and their development were introduced in this paper.     

A half century of radioisotope neutron sources in China

Near 50 years history of the development of radioisotope neutron sources in China is briefly reviewed. The structure design, preparing technology and production status of routine neutron sources including 210Po-Be sources, 210po mock fission sources, 241 Am-Be sources, 238pu-Be sources, 252Cf spontaneous fission sources and other special-shape neutron sources are summarized. In addition, the prospects of development on radioisotope neutron source in China are predicted from the needs of nuclear power construction, oil well-logging, neutron moisture gauge and neutron brachytherapy.