大亚湾中微子实验波形数据获取软件设计

介绍了大亚湾中微子实验波形数据读出和数据压缩算法的数据获取软件设计。该软件是以大亚湾中微子实验数据获取系统为基础,在不影响现有电子学系统正常取数的前提下,针对一号实验厅新增的一套前端电子学系统实现波形数据的网络读出、检查、组装、压缩和存盘等功能的软件系统。文中详细说明了波形数据的读出流程以及不同数据压缩方法的实现,并给出了软件的长期稳定性测试结果。     

大亚湾中微子实验时钟时标广播系统的初步设计

使用高速光纤、嵌入式系统以及高速FPGA,清华大学高能中心的研究人员为大亚湾反应堆中微子试验三个实验站点的时钟和时间分配研制了先进的时钟系统.论文讨论时钟系统的实现原理和具体设计,并对初步实验过程和结果进行了讨论.     

Neutrino method remote measurement of reactor power and power output

Conclusions The neutrino method is essentially a remote method and does not require contact with the elements of the reactor. The accuracy and reproducibility of the neutrino procedure in measurements of the power and power output of the VVéR-540 reactor are close to the data obtained with thermal measurements. For other types of reactors the neutrino method can be more accurate than the traditional methods. The neutrino method makes it possible to monitor plutonium production directly during the plutonium production process. It is possible to develop a method of neutrino tomography for monitoring the spatial nonuniformity of energy release in the fuel core of the reactor as well as methods for monitoring in the case of accidents. Neutrino installations are now portable and compact, and they can be further improved. We are not offering the neutrino method as an alternative to other methods of monitoring, which have been checked over a period of many years, but rather we regard it as a method for extracting additional information in order to obtain a more complete picture of reactor operation. We thank A. G. Vershinskii for providing the electronics for the experiment, and I. N. Machulin for helpful discussions and for calculating the composition of the fuel core, and the management and personnel of the nuclear power plant for assistance. Institute of General and Nuclear Physics, Russian Scientific Center "Kurchatovskii institut." Translated from Atomnaya énergiya, Vol. 76, No. 2, pp. 130–135, February, 1994.     

DRAGON用于反应堆中微子实验的基准验证

反应堆中微子实验中需计算输出²³⁵U、²³⁸U、²³⁹Pu、²⁴¹Pu在不同燃耗下的裂变份额,而通常的组件计算程序不输出这些结果。为适应反应堆中微子实验的需求,本文用Takahama-3基准对DRAGON用于压水堆燃耗进行基准验证,给出了反应堆中微子实验中关心的4种核素质量密度实验值与计算值的平均偏差,并利用计算出的裂变份额以及每次裂变释放的能量等,给出了NT3G24组件的反应堆中微子能谱,从而验证了DRAGON应用于反应堆中微子实验的可行性。     

大亚湾中微子实验光电倍增管输出振铃脉冲的分析研究

大亚湾反应堆中微子实验是一个研究中微子振荡的实验[1],主要目标是利用核反应堆产生的电子反中微子来测定一个具有重大物理意义的参数—中微子混合角θ13。大亚湾中微子实验的目标是将sin22θ13测量到0.01或更高的精度,为实现对大亚湾中微子信号的准确测量,必须要求光电倍增管输出干净脉冲信号到前端电子学(FEE),但在测试实验中,发现光电倍增管输出脉冲含有振铃。针对振铃进行了详尽分析,找到了振铃产生的根源,也确认了电容在高压下的压电效应。     

Inverse Problem of Neutrino Diagnostics of In-Reactor Processes

The inverse problem of neutrino diagnostics of a reactor core is examined using existing experimental data. Solving this problem, on the one hand, makes it possible to reconstruct by remote control and to high degree of accuracy the instantaneous nuclear density of each component of the nuclear fuel and, on the other, opens up a realistic possibility of developing a neutrino technology for on-line diagnostics of the temporal evolution of the reactor power and the isotopic composition of nuclear fuel.     

百万千瓦级核电厂~(16)N监测仪系统验证和确认

为保证百万千瓦级核电厂~(16)N监测仪系统中软件的可靠性和安全性,引入了验证和确认(VV)技术。本文阐述了~(16)N监测仪的开发过程中是如何建立VV组织和体系,高质量地执行VV活动,研究了执行VV活动新的方法和工具,评估了VV活动的质量,可为其他1E级设备的VV活动提供指导和参考。     

Yale - NAL CAMAC System

A data acquisition system for high energy physics experiments is described here, which is in accordance with the specifications of EUR 4100e and EUR 4600e. This is a multicrate system using branch highway and type A crate controllers. Most of the components are now commercially available.     

Density-wave oscillations in parallel channels - an analytical approach

Density wave oscillations in parallel channel systems are analytically investigated. A new model is presented, from which explicit expressions are obtained for the stability limits and periods of oscillation of a two-identical channel system. The two modes correspond to the channels oscillating in-phase or out-of-phase, in both cases with the same amplitude.A two-channel system with a power skew is then analyzed with two different approaches. In the first approach a pertubative methods is used, which shows that the normal modes are no longer the in-phase and out-of-phase ones.In the second approach of a fourth order eigenvalue problem is solved with a computer. For different power skews the stability thresholds, amplitude ration and phase difference between the oscillations of the variables of the two channels and the periods of oscillation are obtained. It is also shown that larger power skews make the system more unstable, except in the very low inlet subcooling region.     

CBM-TOF超级模块高密度数据前端读出设计

为满足超级模块探测器质量评估的数据读出需求,设计了一种基于"三明治"结构的前端高密度数据读出方法。利用FPGA技术实现320通道时间数字化数据读出和自定义协议处理,并通过片内高速串行收发器与光纤进行长距离数据传输。在外部回环模式下的测试结果表明,6 Gb/s高速链路误码率小于10-13的置信度超过95%,接收TDC数据和自定义协议处理功能正常,系统连续稳定运行超过48 h,可满足探测器评估需求。     

PIUS - status and perspectives

Today's environmental concerns show that nuclear energy is an important option for meeting future increases in global energy demand. Significant nuclear expansion will probably require new reactor designs in which safety is ensured by simple, convincing means. PIUS represents such a reactor design. It is a re-configured 600 MWe PWR, in which the primary safety goal, protection of the reactor core integrity, is entrusted to built-in, self-protective, passive features, without reliance on any monitoring, detection or actuation system, nor operator action. Its basic design features a core that is openly connected, in a natural circulation loop, to a large pool of borated water. The pool is enclosed in a prestressed concrete pressure vessel provided with redundant leakage barriers. The reactor coolant pumps are operated in such a way that there is hydraulic balance in the openings between the primary coolant loop and the pool. Thereby, the hot, low boron content primary loop water is kept separated from the pool water, in spite of the always open natural circulation loop. In severe transients this balance is disturbed, and pool water ingress occurs, shutting down the reactor, or restricting the power to a safe level. The decay heat is transferred to the pool by the natural circulation loop, and a passive pool cooling system, utilizing natural circulation and natural draft cooling towers, prevents boiling of the pool water, even in a station blackout situation. Transient analyses have shown that this passive long-term RHR function will be available in all accident situations, even after double-ended cold leg breaks. Such breaks result in a temporary pressurization of the reactor containment, but the releases of radioactivity will be extremely small and the doses at the fence boundary very low. Cost estimates indicate that PIUS will be quite competitive, and evaluation studies are now under way in several countries.     

Natural circulation loops with parallel channels - transient behavior

A theoretical modeling method is presented for describing the transient flow and heat transfer in natural circulation loops. The system under consideration includes a common heat source and a general number of parallel branches having a heat sink (heat exchanger). The conservation continuity, momentum and energy equations are written, based on a one dimensional approach. The momentum equation it integrated around every closed loop such that the pressure terms are eliminated and the energy equation is integrated separately for every component. This procedure leads to a set of simultaneous ordinary differential equation for the time dependent flow rates and average component temperatures. The equations are solved numerically using a combination of explicit and implicit techniques. The method has been applied to a small scale 4-loop system relevant to a PWR. Several transients have been traced and the agreement with available data is quite good.     

OGO-E Cosmic Radiation - Nuclear Abundance Experiment

Information on the detailed charge and energy spectra of galactic and solar cosmic rays is required for a better understanding of the production, acceleration and modulation of those cosmic rays. This experiment consists of a set of three detector assemblies to measure the differential energy spectra of protons and heavier nuclei through calcium (Z = 20) in the range of 400 Kev to 1 Bev/nucleon, and an extensive electronics system to implement the logic, perform pulse height analysis, measure particle fluxes, monitor experiment performance and interface with the OGO data system. The detector systems described here are the design of F. B. McDonald, V. K. Balasubrahmanyan, D. E. Hagge, B. Teegarden and G. H. Ludwig of the Goddard Space Flight Center.     

改进核电厂场外环境γ连续性监测系统的有关设想

从广东大亚湾／岭澳核电站场外环境γ连续性监测系统的建设改造需要出发，针对监测系统的仪器选型、监测子站的分布、数据传输手段和系统软件开发等问题进行了初步探讨，对进一步改进核电站场外环境γ连续性监测系统提出几点初步设想。     

CAMAC Instrumentation System - Introduction and General Description

The CAMAC instrumenatation system developed by the ESONE Committee of European laboratories has been endorsed by the U. S. AEC NIM Committee as a dataway system complementary to the NIM (Nuclear Instrument Module) system. CAMAC is described in a general way in this introductory paper which is followed by papers that discuss the system in greater detail and describe typical implementation.     

UNIX - A Solution to the Conpatibility Problem

The UNIX operating system (TM Bell Laboratories) has achieved a high degree of popularity in recent years. It is rapidly becoming a defacto standard as the operating system for 16 and 32 bit microcomputers. The adoption of this operating system by the physics community offers several substantial advantages; a portable software environment (editors, file system, etc.), freedom to choose among a variety of higher-level languages for software applications, and computer hardware vendor independence.     

CAMAC Instrumentation System - Introduction and General Description

The CAMAC instrumentation system developed by the ESONE Committee of European laboratories has been endorsed by the U. S. AEC NIM Committee as a dataway system complementary to the NIM (Nuclear Instrument Module) system. CAMAC is described in a general way in this introductory paper which is followed by papers that discuss the system in greater detail. This paper is an updated version of the introductory paper that appeared in the April 1971 IEEE Transactions on Nuclear Science.     

Nuclear energy and waste management - pyroprocess for system symbiosis

The actinide management has become a key issue in nuclear energy. Recovering and fissioning transuranium elements reduce the long-term proliferation risks and the environmental burden. The better way of waste management will be made by system symbiosis: a combination of light-water reactor and fast reactor and/or accelerator-driven transmutation system should be sought. The new recycling technology should be able to achieve good economy with smaller plants, which can process fuels from different types of reactors on a common technical basis. Ease in handling the higher heat load of transuranium nuclides is also important. Pyroprocesses with the use of molten salts are regarded as the strong candidate for such recycling technology. In JAEA, the first laboratory for the high-temperature chemistry of Am and Cm has been established. The fundamental data will be combined with the computer code for predicting the molten-salts electrolytic processes.     

A generic semi-implicit coupling methodology for use in RELAP5-3D

A generic semi-implicit coupling methodology has been developed and implemented in the RELAP5-3D^© computer program. This methodology allows RELAP5-3D^© to be used with other computer programs to perform integrated analyses of nuclear power reactor systems and related experimental facilities. The coupling methodology potentially allows different programs to be used to model different portions of the system. The programs are chosen based on their capability to model the phenomena that are important in the simulation in the various portions of the system being considered and may use different numbers of conservation equations to model fluid flow in their respective solution domains. The methodology was demonstrated using a test case in which the test geometry was divided into two parts, each of which was solved as a RELAP5-3D^© simulation. This test problem exercised all of the semi-implicit coupling features that were implemented in RELAP5-3D^© The results of this verification test case show that the semi-implicit coupling methodology produces the same answer as the simulation of the test system as a single process.     

《辐射防护规定》的剂量限制体系

《辐射防护规定》(GB8703-88)结合我国具体情况采纳了国际放射防护委员会(ICRP)第26号出版物所推荐的剂量限制体系。剂量限制体系主要适用于所有可控制源的防护,它规定了辐射防护的目的和基本原则,各种剂量限值及对公众照射的限制原则。本文着重阐述《辐射防护规定》中剂量限制体系的制定依据和主要特点。文中还对与实施剂量限制体系有关的一些问题作了说明。