上海市钢铁工业尘单颗粒分析

用高分辨率、高灵敏度的扫描质子微探针对上海市工业尘进行单颗粒分析,研究了在颗粒物中不同元素的分布以及元素平均含量随粒径大小的变化。结果表明,Fe、Cr、Mn等元素在颗粒物中均匀分布的,而K、Ca则富集在颗粒物的表面。而且这些元素的平均含量随粒径的变化呈现出一规律性,其中大部分重金属元素（如Cu、Cr、Ni、Zn、Pb）聚集在颗粒粒径＜5μm的颗粒物上。     

Multi-technique characterizations of main elements in the vehicle exhaust particles collected in a tunnel in Shnaghai

In this study,vehicle exhaust particles were collected three locations (the middle,entrance and outside) of the Dapu Road tunnel in downtown Shanghai,and the particle samples were characterized using SEM,XAFS,ICP-MS and M?ssbauer spectrometry,and the oxidative damage was assessed by plasmid DNA.Most iron-containing particles are found from vehicle exhaust,and iron oxide is the major species in all samples.Its concentration in the particles inside the tunnel is higher than that the outside particles.The iron particles inside the tunnel have higher proportion of water-soluble fraction in hydrous iron sulfate form or smaller size.ZnCl2 is the main soluble fraction in zinc-containing particles,while higher percentage of insoluble fraction existed in the particles outside of tunnel.Major species of lead-containing particles are PbSO4,Pb3(PO4)2 and PbCO3.In addition,the soluble fraction of other transition metallic elements as Ti and V is higher in the particles inside the tunnel than that outside the tunnel.The plasmid DNA assay results indicate that the particles from vehicle exhaust have a stronger oxidative damage and inflammation than that from outside of the tunnel.     

尖晶石－石榴石相转变过程中矿物的微量元素组成与分布特征

利用质子微探针和微束ＰＩＸＥ定量分析技术对山东梭罗树地慢橄榄岩中橄榄石、斜方辉石、单斜辉石、尖晶石和石榴石等矿物的微量元素组成与分布进行了研究。结果表明，不相容元素（Ｓｒ、Ｙ、Ｚｒ）主要富集于单斜辉石内，尖晶石则几乎富集质子探针所能检出的所有微量元素，而石榴石中微量元素含量最少。该研究表明，在矿物微区微量元素分布是十分不均匀的，推测可能受地幔交代过程中溶液的渗滤效应以及存在微粒包裹体的共同制约。     

Source apportionment of single aerosol particles in the atmosphere of Shanghai city

A nuclear microprobe with high spatial resolution and high analytical sensitivity was applied to analyze atmospheric aerosol at five monitoring sites in Shanghai city.Meantime,a new pattern recognition technique,which used the micro-PIXE spectrum of a single aerosol particle as its fingerprint.was developed to identify the origin of the particle.The results showed that the major contributors to the atmosphere pollution were soil dust(31.6%) ,building dust(30.8%),and the next were vehicle exhaust(13.7%),metallurgic industry excrements(5.6%).oil combustion(5%) and coal combustion(2.3%).Besides these ,about 10% of the particles could not be identified.Based on the cluster analysis of these particles.they could be divided into eight groups.By inference,they might belong to some sub-pollution sources from soil dust,building dust and metallurgic industry excrements.Moreover,some new pollution sources from tyres and chemical plants were also revealed.     

核辐射突发事件医学应急的现场救援及组织指挥原则

根据核辐射突发事件医学应急现场救援的具体任务和需要的处置力量,将其分为小规模核辐射突发事件、中等规模核辐射突发事件和大规模核辐射突发事件,并具体分析了各自的特点、危害、现场医学救援的任务和技术力量。重点针对＂脏弹＂恐怖袭击,介绍了现场医学救援的主要任务,以及污染控制和伤员救治的技术流程。为更好地执行核辐射事故现场医学救援任务,总结并提出了组织指挥中应该注意的几个原则,包括快速反应原则、剂量限值原则、防护最优化原则、权衡利弊原则,以及辐射监测、去污控污、伤员救治等核心任务的全流程贯穿原则等。     

氦中痕量H2、D2组分的高精度气相色谱分析

为满足聚变堆氘氚燃料循环工艺气体中痕量氢同位素组分的特殊检测分析要求,需建立快速、高精度的在线分析方法。针对氦中痕量H₂、D₂组分,本工作以高纯氦为载气,在液氮温度下,使用自制改性Al₂O₃毛细管柱进行分离,放电氦离子化检测器进行检测。结果显示,氢氘组分的检测限不高于1×10^-8,保留时间不高于180 s,氢氘组分色谱峰峰面积响应值的相对标准偏差不大于1.0%,分离度大于1.0。本方法具有分析灵敏、快速的优点,为聚变堆包层在氘氚燃料注入系统和氢同位素分离系统中微量氚的安全分析与精确计量提供了一种有效的测量技术。     

氦中痕量杂质气体气相色谱检测分析方法研究

为实现聚变堆氘氚燃料工艺气中痕量杂质气体组分的快速检测分析,需建立特殊的高精度在线气相色谱检测分析方法。以高纯氦作为载气,在不同的色谱柱温度和载气流速控制下,通过分子筛毛细管柱和PLOT-Q柱进行分离,采用放电氦离子化检测器（DID）进行检测,对氦中含量为1、10以及100 ppm的杂质标准气体进行检测分析。结果表明：在柱温为40 ℃、流速为15～20 mL/min实验条件下,分子筛柱在160 s内能够实现H₂、O₂、N₂、CH₄和CO全部分离,且柱效较高,响应值的重复性较好,H₂和O₂之间的分离度高于1.5,实现了完全分离;在柱温为40 ℃、流速为20 mL/min时,PLOT-Q柱分离CO₂组分效果最佳。     

A Proposal for cooperative activities between Japan and Indonesia in the field of Nuclear research and Nuclear education

Development and realization of cooperative activities between Japan and Indonesia in nuclear research and education is indeed very important for scientists and engineers of both countries. This bilateral cooperation can easily be expanded into a regional cooperation benefiting the scholars from Asian region which is expecting a New Nuclear Age in the 21st Century.

To develop and realize this cooperative activities, in the first step, we invite the ideas of our partners in the Nuclear Institution and in Universities. They are eager to have and undertake this cooperation effort. For nuclear research activities, they have proposed several topics which include: advanced radioactive waste technology and management in a nuclear power plant, innovative fuel development for LWR's, gas cooled reactor for electricity and hydrogen production and a topic on design and construction of high energy accelerator.

Institute of Technology – Bandung (ITB), University of Gajah Mada (UGM) and School of Nuclear Technology (STTN/BATAN) are interested in cooperative works which include: joint development of standard curriculum for M.Sc. level in response to increased activities in nuclear research and nuclear power development, exchange of guest lecturers, and exchange of M.Sc. level students. With this cooperation, we want to put very special emphasis on nuclear human resources development (nuclear – HRD) in anticipation of the upcoming nuclear era.     

Assessment of thermal aging embrittlement in a cast stainless steel valve and its effect on the structural integrity

This paper analyzes the thermal aging embrittlement occurred in a cast stainless steel valve, which is part of the reactor water clean-up (RWCU) system of a Spanish boiling water reactor (BWR) nuclear power plant. The aim is to estimate the current and future state of the material and the corresponding structural integrity of the valve. Given that there is no data available for the experimental characterization of the material, the evolution of the mechanical properties (fracture toughness, yield stress, flow stress and Ramberg-Osgood parameters) has been estimated using the ANL procedure.With the obtained estimations, the critical crack size has been calculated using the European procedure FITNET FFS and the ASME Code.This analysis considers not only the evolution of the mechanical properties up to now but also its future evolution in case there is a life extension of the plant until year 2029.     

Analysis of radionuclide retention in water pools

An analysis is presented of the removal of aerosol particles and gaseous fission products from steam-noncondensable gas mixtures rising through water pools. The pool is divided into a gas injection zone, a bubble rise zone and a pool surface zone. The formulation of the governing conservation equations is relatively general with a quasi-steady one-dimensional formulation for the gas phase, and an unsteady, well stirred, formulation for the liquid phase. An associated computer code for performing the calculations, SUPRA, is described. Results of parametric calculations are given for conditions expected in a BWR severely degraded core accident sequence. Parameters studied include aerosol particle size and distribution, mass fraction of noncondensable gas, gas mass flow rate, quencher submergence depth, and pool water temperature.     

CFD evaluation of hydrogen risk mitigation measures in a VVER-440/213 containment

In the PHARE project “Hydrogen Management for the VVER440/213” (HU2002/000-632-04-01), CFD (Computational Fluid Dynamics) calculations using GASFLOW, FLUENT and CFX were performed for the Paks NPP (Nuclear Power Plant), modelling a defined severe accident scenario which involves the release of hydrogen. The purpose of this work is to demonstrate that CFD codes can be used to model gas movement inside a containment during a severe accident. With growing experience in performing such analyses, the results encourage the use of CFD in assessing the risk of losing containment integrity as a result of hydrogen deflagrations. As an effective mitigation measure in such a situation, the implementation of catalytic recombiners is planned in the Paks NPP. In order to support these plans both unmitigated and recombiner-mitigated simulations were performed. These are described and selected results are compared. The codes CFX and FLUENT needed refinement to their models of wall and bulk steam condensation in order to be able to fully simulate the severe accident under consideration.Several CFD codes were used in parallel to model the same accident scenario in order to reduce uncertainties in the results.Previously it was considered impractical to use CFD codes to simulate a full containment subject to a severe accident extending over many hours. This was because of the expected prohibitive computing times and missing physical capabilities of the codes. This work demonstrates that, because of developments in the capabilities of CFD codes and improvements in computer power, these calculations have now become feasible.     

Capabilities of TRANSURANUS code in simulating power ramp tests from the IFPE database

Investigations of fuel behavior are carried out in close connection with experimental research, operation feedback and computational analyses. OECD NEA sets up the “International Fuel Performance Experiments (IFPE) database”, a public domain database on nuclear fuel performance experiments with the purpose of model development and code validation. The objective of the activity (performed in the framework of the IAEA CRP FUMEX-III project) is to investigate the pellet-clad interaction mechanism and the capability of TRANSURANUS code in simulating the phenomena, processes occurring in the fuel rod during the power ramps, with focus on the parameters influencing the cladding failures. The experimental database adopted is the Studsvik PWR Super-Ramp subprogram, part of the IFPE database, which consists of 28 pressurized water reactor fuel rods power ramped at burnup from 28 to 45 MWd/kgU. Relevant results by TRANSURANUS are presented in connection with the experimental evidences. Focus is given on the PCI/SCC failure, demonstrating that the failure threshold, available in TRANSURANUS, results conservative both in case of KWU and W rods.