核燃料燃耗的质谱测定

研究和评论了目前使用在核燃料燃耗测定中的各种方法,并着重讨论了破坏性燃耗测定的质谱法。质谱法包括重元素同位素丰度比法和同位素稀释质谱法。重元素同位素丰度比法只适用于深燃耗,而燃耗监测体法适用于各种燃耗水平。最后,根据实践经验,提出了质谱法燃耗测定中值得注意的几个问题。     

用质谱法测量反应堆元件的燃耗

文章介绍了用质谱计测量反应堆元件的燃耗的基本方法,铀同位素比值法和燃耗监测核素~(148)Nd含量测定法的测量误差分别是(3.0—4.0)％和(1.6—2.0)％。用质谱法获得的燃耗值与用γ谱法和放化法获得的燃耗值是一致的。 文章给出了铀同位素比值、α_5值和燃耗值沿反应堆元件轴向的分布曲线,铀同位素比值与燃耗值的关系曲线。铀同位素比值和燃耗值的关系曲线是线性的,它与裂变生成的毒物核素~(149)Sm同燃耗的关系曲线是一致的。     

反应堆燃料元件燃耗测量中的质量控制

从人员培训、实验方案的改进与优化、仪器试剂的选用及检测和准确测量、环境剂量的监测与控制等几方面,介绍了中国核动力研究设计院在反应堆燃料元件燃耗测量工作中严格质量控制的情况,包括认真执行管理程序,利用先进的检测手段和实验方法,减少了人员所受辐射剂量,提高了样品分离速度和效果,降低了测量结果的不确定度,确保了燃耗测量工作的质量要求。     

HFETR燃料元件燃耗测定的重同位素方法研究

本文推导和研究了适用于高通量工程试验堆燃料元件燃耗测定的重要公式,并将ASTM E244的公式作了重要修改。燃耗值的不准确度可达到3％,与Nd标准方法最大偏差为2％,为重同位素方法使用提供了新公式。     

板型燃料元件燃耗自动测量系统设计

现有的板型燃料元件的燃耗无损测量自动化水平较低,只适用于单点测量。结合板型燃料元件的结构特点及燃耗测量要求,设计板型燃料元件自动测量系统。自动测量系统集成了交互式测点规划、运动系统控制、γ能量谱仪控制、数据处理及结果可视化功能,实现了板型燃料元件多点、分段、自动化、无损燃耗测量。系统运行结果表明:该系统可靠性高,操作简单,能够有效地提高测量效率、精度,降低操作人员的工作量。     

10MW高温气冷堆的燃耗测量研究

10MW高温气冷堆的燃耗测量系统是采用非破坏性高纯锗γ谱仪在线监测来确定燃耗值,利用MCNP4A程序对测量系统的衰减因子进行计算,基于核燃料裂变核素的γ射线能谱分析,以137Cs和134Cs核素活度作为测量对象,并对燃耗测量结果进行讨论.     

反应堆卸料元件燃耗的质谱测定

本文介绍了用质谱法测定反应堆卸料元件燃耗的原理,燃耗监测体~(145+146)Nd,~(148)Nd,~(150)Nd和~(98)Mo 的测定,以及有效裂变产额的计算和比较。     

西安脉冲堆燃料元件燃耗无损实验测量

介绍了西安脉冲堆燃料元件燃耗测试理论、所用设备及实验方法,重点阐述了燃耗测量中用到的中子/γ自吸收校正、127 Cs活度校正、探测效率标定等关键技术.对堆芯内两根具有代表性的燃料棒D5、G14开展了燃耗测量,并工理论计算结果进行了比较.结果表明:燃耗测量结果与理论估算值在不确定度范围内一致,该燃耗测试分析系统是可靠、适用的.     

球床式高温气冷堆在线燃耗测量中^239Pu的影响分析

高温气冷堆中,燃料的平均燃耗比较深.随着235U的消耗和239Pu的累积,239Pu的裂变就将成为一个不可忽略的部分.通过理论计算,讨论了239Pu的裂变对于燃耗测量的影响.计算表明,当燃料球燃耗达到80 000 (MW·d)/t (U)时,239Pu的裂变所贡献的燃耗份额约26.7%,239Pu裂变产生的137Cs和134Cs分别占其各自总活度的27.2%和23.2%;比较而言,利用137Cs活度来计算燃耗的方法比用活度比134Cs/137Cs好.     

Measurement of Burnup in FBR MOX Fuel Irradiated to High Burnup

The burnup of fuel pins in the subassemblies irradiated at the range from 0.003 to 13.28%FIMA in the JOYO MK-II core were measured by the isotope dilution analysis. For the measurement, 75 and 51 specimens were taken from the fuel pins of driver fuel and irradiation test subassemblies, respectively. The data of burnup could be obtained within an experimental error of 4%, and were compared with the ones calculated by 3-dimensional neutron diffusion codes MAGI and ESPRIT-J, which are used for JOYO core management system.

Both data of burnup almost agree with each other within an error of 5%. For the fuel pins loaded at the outer region of the subassembly in the 4th row, which was adjacent to reflectors, however, some of the calculation results were 15% less at most than the measured values. It is suggested from the calculation by a Monte Carlo code MCNP-4A that this difference between the calculated and the measured data attribute from the softening of neutron flux in the region adjacent to the reflector.     

质谱法测量碳同位素丰度在气体扩散法分离乙醇中的应用

乙醇是扩散分离碳同位素的一种可行的介质,为得到气体扩散法分离乙醇的分离系数,开展元素分析-同位素比质谱法(EA-IRMS)测量乙醇中碳同位素丰度在气体扩散分离实验中的应用研究。通过文献调研,本研究优化了乙醇样品的制备流程,发展了EA-IRMS用于乙醇碳同位素丰度测定的方法,进行了稳定性测试,实现了对乙醇样品碳同位素丰度的测量。基于气体扩散法的分离实验,获取多次分离实验中精料乙醇和贫料乙醇的碳同位素丰度,经公式推导可计算得到乙醇扩散分离碳同位素的基本全分离系数。本研究为未来开展以乙醇为介质扩散分离碳同位素实验提供了分析基础。     

质谱法测量碳同位素丰度在气体扩散法分离乙醇中的应用

乙醇是扩散分离碳同位素的一种可行的介质,为得到气体扩散法分离乙醇的分离系数,开展元素分析-同位素比质谱法(EA-IRMS)测量乙醇中碳同位素丰度在气体扩散分离实验中的应用研究。通过文献调研,本研究优化了乙醇样品的制备流程,发展了EA-IRMS用于乙醇碳同位素丰度测定的方法,进行了稳定性测试,实现了对乙醇样品碳同位素丰度的测量。基于气体扩散法的分离实验,获取多次分离实验中精料乙醇和贫料乙醇的碳同位素丰度,经公式推导可计算得到乙醇扩散分离碳同位素的基本全分离系数。本研究为未来开展以乙醇为介质扩散分离碳同位素实验提供了分析基础。     

高燃耗陶瓷燃料颗粒的参数化建模及强度分析

弥散燃料芯体中的陶瓷燃料颗粒在辐照条件下会形成裂变气孔,燃料颗粒内部气孔间的相互干涉作用及气孔内压的增长致使局部拉应力超过材料强度极限,进而导致燃料颗粒开裂。本文考虑高燃耗燃料颗粒内气孔尺寸和位置分布的非均匀性,实现了颗粒内部的细观结构参数化建模。运用有限元方法计算并分析了气孔尺寸、基体约束压应力、温度和气孔分布方式对颗粒内部最大拉应力的影响,研究了颗粒内开裂危险区的分布规律。结果表明,陶瓷燃料颗粒最大拉应力随气孔尺寸和温度的增加而增大,随基体约束压应力的增加而减小;燃料相的断裂强度减小,开裂危险区面积增大;燃料颗粒从内部多处开裂破坏,而表层处开裂的概率更大。本文为弥散燃料失效研究及优化设计提供了分析方法及数值参考。     

Fission Product Model for BWR Analysis with Improved Accuracy in High Burnup

A new fission product (FP) chain model has been studied to be used in a BWR lattice calculation. In attempting to establish the model, two requirements, i.e. the accuracy in predicting burnup reactivity and the easiness in practical application, are simultaneously considered. The resultant FP model consists of 81 explicit FP nuclides and two lumped pseudo nuclides having the absorption cross sections independent of burnup history and fuel composition. For the verification, extensive numerical tests covering over a wide range of operational conditions and fuel compositions have been carried out. The results indicate that the estimated errors in burnup reactivity are within 0.1Δk for exposures up to 100GWd/t. It is concluded that the present model can offer a high degree of accuracy for FP representation in BWR lattice calculation.     

Post Irradiation Examination of High Burnup PWR Fuel

Post irradiation examination (PIE) of a high burnt lead fuel assembly, which was irradiated to demonstrate fuel integrity at high burnup, was performed before the start of the full batch loading of high burnup fuel of 48GWd/t maximum fuel assembly burnup.

The lead fuel assembly was 17×17 B-type PWR fuel which was supplied by Nuclear Fuel Industries, Ltd. (NFI) and achieved the maximum burnup of 45 GWd/t after 4 cycles of irradiation in Ohi Unit 1 of the Kansai Electric Power Co. Inc. (Kansai).

Twelve fuel rods extracted from the lead fuel assembly at the reactor site were examined at the hot-cell facility of Japan Atomic Energy Research Institute (JAERI) in Tokai-mura.

Visually, the fuel rods appeared to be in good conditions, but some small spallings were observed at the second span from the top where oxide film was relatively thicker than other spans. Even in this span, the maximum oxide film thickness was less than 50 μm Fission gas release rate was less than 1%, which caused only a small increase in fuel rod internal pressure. Mechanical properties of the fuel cladding were evaluated by tensile tests.

These PIE results were within the range of other PIE data previously obtained from domestic and foreign PWR fuel rods. The data confirmed that the integrity of B-type fuel would be maintained at least up to 48 GWd/t.     

同位素稀释质谱法测定空心玻璃微球内氘气总量

作为惯性约束核聚变(ICF)第一代靶丸,空心玻璃微球(HGM)内充燃料气体的组分、比例和密度均有严格要求,气体总量的测定至关重要。介绍了同位素稀释质谱法(IDMS)测定空心玻璃微球内氘气气体总量的分析方法。该方法采用氢气为稀释剂,活性炭作为吸附剂制备氘气和氢气的混合气体,用质谱计测定样品中氢同位素丰度。通过热力学公式推导、计算,求得HGM内氘气摩尔数。实验结果表明:用IDMS法测量HGM内痕量氘气总量切实可行,其测量下限为10-8 mol,测量结果的相对标准偏差小于5%(n=4或3,按照极差法计算),符合测量要求。     

Oxygen Potentials of UO2 Fuel Simulating High Burnup

The oxygen potentials at 1,000 and 1,300°C and the lattice parameters of UO₂ fuels with soluble fission product elements (Zr, Ce, Pr, Nd, Y), simulating high burnup of up to 10^a,_o have been measured by means of thermogravimetry and X-ray diffraction. The oxygen potentials for (U, FP)O₂+x fuels are higher than pure UO_2+x; at a given composition and increase positively with increasing simulated burnup. They can be represented as a function of the mean uranium valence at compositions of 0/M>2.01. The lattice parameters of stoichiometric (U, FP)0₂.00 fuels decrease linearly with simulated burnup, and can be expressed as a (pm) = 547.02–0.1225, where B is burnup in ^a._o     

Sensitivity Analysis of Fission Product Concentrations for Light Water Reactor Burned Fuel

The accurate prediction of fission product concentrations (FPCs) is necessary for application of the burnup credit to nuclear facilities. In order to specify important nuclear data for the accurate prediction of FPC, we extensively evaluate the sensitivities of FPC to nuclear data with the depletion perturbation theory. The target fission products are twelve important ones for the burnup credit, Mo-95, Tc-99, Rh-103, Nd-143, Nd-145, Sm-147, Sm-149, Sm-150, Sm-152, Cs-133, Eu-153, and Gd-155. The present study successfully specifies the important nuclear data both in a UO₂ cell and in a MOX cell. While the obtained sensitivities are mostly similar to each other between the UO₂ and MOX cells, large differences are observed in some cases, such as the Gd-155 concentration. It is clearly shown that such differences between the UO₂ and MOX cells come from differences in cumulative fission yields between U-235 and Pu-239 and differences in neutron flux energy spectra.     

蒙特卡罗方法在CZT探测器测量乏燃料组件燃耗中的应用

利用碲锌镉（CZT）探测器组成的γ谱探测系统是一种测量乏燃料组件燃耗的较有效的方法。本文利用蒙特卡罗方法,借助于Geant4软件包计算在两种测量方式、多个准直高度条件下组件中¹³⁷Cs和¹³⁴Cs的全能峰探测效率,对测量结果的正确评价分析具有一定意义。另外,采用偏倚抽样方法确定源粒子发射方向,极大提高了CZT探测器全能峰探测效率。