核电站重要仪表测量通道的不确定度计算方法

对核电厂重要仪表测量通道的不确定度计算的相关国内核安全法规要求、最新国际标准进行了研究,提出一套测量通道不确定度计算的方法。总结完善了计算方法中不确定度通道的类型、国产化仪表设备的不确定度项区分、环境条件区分以及整定值的确定等内容,演示了采用该方法进行仪表测量不确定度计算的过程,并给出了计算结果。通过相关计算,验证了该方法对维护核电厂原有安全基准的有效性。相比较于同类计算方法获得的结果,新计算方法具有明显的优越性。     

Optimization of in-core fuel management strategy of Tehran Research Reactor (TRR) using MCNP-4C

In order to optimize fuel utilization in TRR, the method of fuel management is modified using MCNP-4C code system. An important parameter of fuel management is the uniformity of neutron flux distribution in the core region, which is obtained efficiently in the present strategy. This strategy is based on calculation of position factors and power densities utilizing MCNP simulations. This study shows that the core life time and average extracted burn up of spent fuel elements of TRR are improved significantly.     

Development of a low-level setup for gamma spectroscopy: Application for nuclear astrophysics using reverse kinematics

It is more and more necessary to improve the sensitivity of gamma-ray spectroscopy systems, especially in nuclear astrophysics. In the case of radiative proton capture reactions, one means is to avoid the reactions on the target impurities by using reverse kinematics. This technique is possible with the LARN accelerator and can provide very clean cross-section measurements. For that purpose, a hydrogen standard has been carried out by means of ion implantation in silicon. In addition, a low-level setup has been put in place on a new beam line of the accelerator. A high efficiency and high resolution germanium detector is used conjointly with a double shielding. A passive lead castle shielding system is used to reduce the natural radioactivity and an active shielding consisting of an anti-cosmic veto is provided by an anticoincidence between the plastic scintillator and the gamma-ray detector. The setup allows a reduction of 70% of the background interference and provides an approximately 200 fold sensitivity gain of between 600 and 3000 keV. Some other developments have also been carried out to optimize the setup. The entire setup and the reverse kinematics have been validated by measuring the cross-section of the ¹³C(p,γ)¹⁴N and ¹⁵N(p,γ)¹⁶O reactions that present some astrophysical interest.     

200MW低温供热堆非对称运行数值研究

采用三维的计算流体力学（CFD）程序PHOENICS－3．3模拟了非对称运行条件下200MW低温供热堆内的流场及温度场,堆芯及主换热器使用多孔介质方法加以简化,结果发现,偏环运行时工质在上下腔室完全混合,不会产生偏心现象,模拟的两种运行方式差别不大,故采用两种运行方式都行。     

核电站机组大修的工期控制难点与优化

根据多年核电站大修管理经验,就核电站机组大修工期控制的难点和关键问题进行探讨,提出相应解决策略。     

核供热系统设计参数的优选

本文依据系统工程原理,把某工程的核供热厂、峰荷热源、热力网、热力站以及热用户作为一个系统,以综合经济效果最佳为目标,充分考虑供热设计和运行的实际条件,建立数学模型,寻求四个基本参数的最佳组合和较佳范围。     

福建惠安核电厂址大气扩散野外示踪试验研究

描述了于2002年夏季在福建惠安核电厂址进行的SF6示踪试验及其主要结果。共进行了15次SF6示踪试验,其中释放高度为70m的五次,30m的六次,10m的四次。天气类型若按?T-U分类,B,C,D,E类天气分别出现3,2,9,1次,若按?T分类,B,D,E类天气分别出现1,11,3次。每次约取50个样品,最远取样点距释放SF6的铁塔15km左右。基于这次试验给出了适用于该厂址各类天气条件下的扩散参数,最后把试验推荐的扩散参数与P-G曲线,Briggs扩散参数以及以往在该厂址进行的湍流测量与风洞模拟实验推荐的扩散参数进行了比较分析。     

压水堆核电厂的核清洁工作介绍

核清洁是保障核电厂安全、高效运行的基础。本文阐述了核清洁工作的技术要求、管理方法和实施步骤,并对未来的工作提出建议。     

核事故条件下的大气扩散模式及应用

本文介绍一个适用于核事故条件的大气扩散模式(粒子-烟团模式)的建立与调试。模式在模拟大气扩散的粒子随机游走方法中引入类似于扩散烟团的核函数概念，用以反映单个随机游走粒子所代表的污染物质的空间影响范围。模式解决了随机游走粒子与核函数“烟团”耦合后反映扩散物理真实过程的一致性问题，在约200km的范围内模拟结果与理论结果相一致。与代表实际大气典型扩散状况的高斯烟羽模式的结果进行定量比较，表明本模式结果在10km的范围内总体合理，但在近源处有系统偏小。模式瞬时浓度的涨落相对于平均轴线浓度大体控制在20％～30％的范围内。将模式应用于秦山地区的实际地形和气象条件进行实例测试表明，其结果可以反映当地复杂的大气扩散过程和特性。     

水力驱动控制棒冷态极限落棒能力分析

为了验证控制棒水力驱动系统在卡棒和倒置等极限工况下的停堆可靠性,在200MW低温核供热堆控制棒水力驱动系统的1：1实验台架上进行了冷态极限落棒实验,通过对实验结果的分析。得到了在发生卡棒事故时控制棒的落棒能力,揭示了落棒机理,建立了正置时控制棒插入堆芯的模型,并用实验数据验证了该模型的正确性,建立了倒置时控制棒插入堆芯的模型,获得了倒置时控制棒的插棒能力。