上海宽波段自由电子激光用户装置高亮度注入器的微波系统

上海宽波段自由电子激光用户装置高亮度注入器的相位相干的４７６ＭＨｚ和２８５６ＭＨｚ的两路微波系统,分别馈送微波功率到射频ｎｓ栅控电子枪,次谐波聚束器和基波涑 器等。介绍了这两个系统的主要组成部件的工作原理,技术指标,安装调试和测试结果。     

SFEL束流偏转传输系统的设计

上海宽波段自由激光用户装置正在中国科学院上海原子核研究所ＦＥＬ实验室设计建造。这里介绍了两个典型偏转系统的设计考虑，并讨论了设计结果。     

Design optimization of 3.9 GHz fundamental power coupler for the SHINE project

The third harmonic superconducting cryomodule is being designed for the Shanghai High repetition rate XFEL and Extreme light facility(SHINE)project,which is under construction.In contrast to the European X-ray Free Electron Laser(E-XFEL)project,the 3.9 GHz cryomod-ules in the SHINE project will operate in the continuous wave regime with higher radio frequency average power for both cavities and couplers.We propose a 3.9 GHz fundamental power coupler with an adjustable antenna length,for satisfying the SHINE project requirements.Here,we describe the 3.9 GHz fundamental power cou-pler's design considerations and power requirements for various operating modes of the SHINE Linac.We also present the results of the radio frequency simulation and optimization,including the studies on multipacting and thermal analysis of the proposed 3.9 GHz coupler.     

SFEL高亮度注入器的设计和粒子动力学特性

使用国际通用程序ＥＴＰ，ＰＡＲＭＥＬＡ和自编程序ＰＬＳ－ＩＭ－６０等对高亮度注入器作了详细的优化设计和粒子动力学数值模拟，注入器出口的电子束品质的主要参数为：能量３．５ＭｅＶ，能散２％（６２％电子）微脉冲束团相宽～４ｐｓ（６２％电子）在第一根加速管出口的电子品质的主要参数为：能量３３ＭｅＶ，能散０．３％（６２％电子）微脉冲峰值电流～８０Ａ，束团相宽３ｐｓ（６２％电子）束归一化发射度２０－３０πｍｍ     

The Year 2015 Fusion Power Conversations

Assuming significant technical success in the ITER project by the year 2015, it is likely that governments will want to develop a more comprehensive plan for DT tokamak fusion power commercialization. To provide a glimpse into many of the related issues, we construct conversations between the director of the U.S. fusion program and three specialists key to commercial fusion success: an environment and safety regulator, an environmentalist, and an electric generation investor. The insights from these imagined conversations will hopefully be of value as tokamak fusion power proponents plan beyond ITER.     

Transportable nuclear power facilities in the INPRO International Project

Questions concerning safety, nonproliferation, monitoring of nuclear materials, civilian responsibility for nuclear risks, physical protection, transport operations, and others are analyzed within the framework of the INPRO project in application to transportable nuclear energy facilities. Essentially, the operative nuclear law and the experience of world nuclear power make it possible to solve the problems of the legal basis for the life cycle of transportable nuclear power facilities. To attain a system with the optimal accessibility, effectiveness, and safety, the nuclear power facilities will have to be adapted to the new specific requirements and conditions, and the international legal basis will have to be made more precise.     

The NIKE KrF laser fusion facility

NIKE is a second generation high power KrF laser now under construction at the Naval Research Laboratory. The project is a collaborative effort between NRL and Los Alamos National Laboratory. NIKE is designed to deliver more than 2 kJ of energy to target in a 600-m focal spot and a 4-ns pulse duration. Echelon free induced spatial incoherence (ISI) will be used to produce uniform target illumination. Flat targets will be ablatively accelerated to study both Rayleigh-Taylor and parametric instabilities. These results will have direct implications to direct-drive inertial confinement fusion for commercial energy applications. Reliable operation of a high power KrF laser is also an important goal of the NIKE laser, with the objective of 1000 target shots per year. This would be an important step in the development of the KrF laser as an ICF driver. NIKE is cheduled to begin target experiments in early 1994. If successful, these experiments will provide a technical basis to proceed with construction of an ignition facility.     

Validation of MAAP model enhancement for Fukushima Dai-ichi accident analysis with Phenomena Identification and Ranking Table (PIRT)

The Modular Accident Analysis Program (MAAP) model enhancement items to improve the simulation capability for molten corium behavior in the accidents at the Fukushima Dai-ichi nuclear power plants were validated with the Phenomena Identification and Ranking Table (PIRT). The importance ranks of the identified phenomena were evaluated for each time phase through brainstorming and discussion with the experts in the Atomic Energy Society of Japan and the members of the MAAP model enhancement project. When the current MAAP evaluation models were reviewed with the PIRT, it is found that 95 of the 386 high-ranked phenomena were not considered in MAAP 5.0.1. While 62 of these phenomena will have been addressed in the MAAP enhancement project and 25 others are not suitable to be analyzed by MAAP, 8 important phenomena should be considered in post-MAAP enhancement project with additional experiments or fundamental studies.     

中国散裂中子源强流质子加速器设计、研制及调试运行

中国散裂中子源（CSNS）是基于强流质子加速器的大科学装置,通过高功率质子束流轰击重金属靶产生高通量中子用于开展中子散射研究,CSNS是世界上第四台、发展中国家第一台脉冲型散裂中子源。CSNS包括高功率强流质子加速器、中子靶站和中子谱仪以及相应的配套设施等。加速器由80 MeV负氢直线加速器、1.6 GeV快循环同步加速器及相应的束流输运线组成。CSNS加速器是我国第一台中高能强流高功率质子加速器,本文将介绍CSNS加速器的设计、关键技术、设备研制以及束流调试过程和其中关键问题。     

Overview of the SNS target system testing and initial beam operation experience

The Spallation Neutron Source (SNS) construction project has been completed including initial beam operation with the mercury target, moderators and associated systems. The project was initiated in 1999, with groundbreaking in December of 1999. Final integrated system testing for the mercury target, cryogenic moderators, shutter systems, water and other utility systems and all control and safety systems were completed in April 2006 and first beam on target was delivered April 28, 2006. This paper will give an overview of the system testing conducted in preparation for beam operation and initial operating experience with low power beams. One area of testing was extensive remote handling testing in the target service bay to demonstrate all key operations associated with the target and mercury loop. Many improvements were implemented as a result of this experience. Another set of tests involved bringing the supercritical cryogenic moderator systems on line. Again, lessons learned here resulted in system changes. Testing of the four water loops was very time consuming because of the complexity of the systems and many instrumentation issues had to be resolved. A temporary phosphor view-screen was installed on the front of the target which has been extremely useful in evaluating the beam profile on the target. Initial profile results will be presented. Target system performance for initial beam operation will be discussed. In general, all systems performed well with excellent availability. There were some unexpected findings. For example, xenon spallation gas products are believed to have deposited on a downstream gold amalgamation bed designed to remove mercury vapor and this disposition increased the local dose rate. A summary of findings and plans for ramping up in power will be given.     

The European pressurized water reactor Result of the French–German cooperation of experienced NPP suppliers and operators

In 1989 Framatome and Siemens, the two most experienced European nuclear power plant suppliers, decided to join the efforts for the development of a new reactor type for the next generation in their equally owned subsidiary Nuclear Power International (NPI). In 1992 Electricité de France and the major German utilities operating nuclear power plants merged their own development programs with that of Nuclear Power International and initiated the European Pressurized Water Reactor (EPR) project. In order to reach the two major targets of the project, the licensability in both countries, France and Germany, and the competitiveness of nuclear energy with other alternative energy sources, the design basis which had differently developed in the two countries needed to be harmonized. In parallel, the licensing authorities of both countries extended their existing cooperation in the field of a safety survey of existing nuclear power plants to the definition of safety criteria for the next generation of nuclear power plants. Through this cooperation the licensability of EPR in France and Germany will be assured. Continuously performed cost analysis show in addition that also the second target of the project, the competitiveness with alternative primary energy sources, can be achieved. Thanks to the fruitful cooperation between all parties involved, satisfactory results have been achieved not by a simple superposition of existing design features but through a careful evaluation and combination of the best available alternatives. At the end of 1997 the basic design results were compiled in a final report. Subsequently an optimization phase was launched that further improves the competitiveness of the power generation costs.     

Desae program for systems studies of long-term growth of nuclear power

The DESAE computer program has been developed, within the framework of the INPRO project implemented under IAEA aegis, as a program complex for making predictive calculations of nuclear power growth. The main purpose of these calculations is to determine the most likely trends in the structural development and scales of the industry and the expected time frames when the new technologies will be needed. Their main benefit lies in the possibility of constructing a balanced picture, as close to reality as possible, of the future structure and developing on this basis a well-substantiated program for strategic scientific-technical policy. A brief presentation of a DESAE calculation of a scenario for nuclear power growth in the country up to 2100 is given. This scenario corresponds to the above-mentioned requirement of balance with respect to the consumption of natural uranium as well as the amount of electricity and heat that will be required. Translated from Atomnaya énergiya, Vol. 105, No. 6, pp. 303–307, December, 2008.     

Upgrades of the tore Supra water cooling system for the WEST project

In ITER, it is foreseen to use an actively-cooled tungsten (W) divertor likely from the beginning of operation. This Plasma Facing Component (PFC) will be subjected to high energy deposition during the plasma operations that severely limit component lifetime. Tungsten has been less extensively studied in tokamaks than carbon. Unlike most present day short pulse fusion devices, Tore Supra is able to reach the ITER pulse length and provide relevant discharges conditions for tungsten PFCs technology validation.A new upgrade of the machine aiming at testing a W divertor under the steady state heat fluxes is being studied in the framework of the WEST (Tungsten (W) Environment in Steady-state Tokamak) project.As the PFC requirements will change, the PFC Primary Heat transfer System (PHTS) must be upgraded. And, even if the injected power in the plasma will not be significantly increased for the WEST project, an upgrade of the Heat Rejection System (HRS) is also needed. This paper presents the studies carried out for these upgrades and the technical solutions to be implemented.     

Ultimate strength of reinforce concrete shear walls under multi-axes seismic loads

“The model test on multi-axes loading on RC shear walls” had been carried out as for the 10-year project aiming at comprehension of the earthquake response behavior of three-dimensional (3D) reinforced concrete (RC) shear walls under the 3D of multi-axes earthquake loading condition. The motivation of the project building-up is that the current seismic design of nuclear power plant building is carried out by applying one-dimensional (1D) dynamic earthquake load to an analytical building model in each direction independently whereas actual earthquake jolts the building in the three directions simultaneously. Therefore, there were opinions requesting some testing confirm whether or not the current seismic design methodology is reliable for the input motions exceeding the design earthquake ground motion moreover for the input motions of the 3D. The project had completed with various valuable outcomes that can reply to the opinions. Moreover, the outcomes will play an important role in evaluating seismic margins of important structures in a nuclear power plant. In this paper, based on the published documents relating to this test project, the author describes a review of the whole testing and summarizes the major outcomes extracted by the test project.     

中国实验快堆工程项目建设的进度管理

中国实验快堆是国内首座快中子反应堆,是国家＂863＂高技术研究发展计划能源领域的重大工程项目。2011年7月21日,中国实验快堆实现并网发电,工程项目建设目标得以实现。作为大型复杂的核电工程项目,进度管理工作是其全部项目管理活动的重要组成部分,文章全面论述了中国实验快堆工程项目建设的进度管理活动。实践证明中国实验快堆工程项目建设进度管理工作的开展科学、规范、高效,对于今后大型快堆核电厂工程建设具有可利用价值,并可资相关领域工作人员进行参考。     

Repair and replacement of reactor internals for plant life extension

Recent experience from early Swedish BWRs corroborate that all components in a nuclear power plant can be repaired or replaced with new ones. Oskarshamn 1 has gone through a thorough refurbishment project. A number of internals were repaired or replaced including the core shroud support which was welded to the bottom of the reactor pressure vessel. The project verifies that it is fully possible to carry out complicated inspection and repair work inside a nuclear pressure vessel which has been in operation for more than 20 years. Along with increased capacity factor, operating nuclear power plants get the financial conditions needed for extensive repair and modernization projects. Large power output leads to short pay-back times for the investments. The FENIX project at Oskarshamn 1 is such a project. There are utilities whose policy is to keep their plants in as-new condition for an unlimited length of time.     

High RF power tests of the first 1.3 GHz fundamental power coupler prototypes for the SHINE project

The Shanghai High Repetition Rate XFEL and Extreme Light Facility(SHINE) project will use 6001.3 GHz fundamental power couplers, which are modified based on TTF-Ⅲ power couplers, for continuous-wave operation with input power up to approximately 7 k W. The first batch of 20 sets of 1.3 GHz coupler prototypes was fabricated from three domestic manufacturers for the SHINE project. To better characterize the radio frequency conditioning phenomena for validating the performance of power couplers, a ...     

秦山第三核电厂反应堆功率变化及模糊控制研究

分析了秦山第三核电厂长期满功率运行时平均功率偏低的产生原因,通过概率统计和计算得到反应堆功率变化的规律,提出了相应的模糊控制方案,并预测了新方案实施后的运行效果.