Data acquisition and control system for lead-bismuth loop KYLIN-Ⅱ-M

Among different heavy liquid metals(HLMs), lead-bismuth eutectic(LBE) is considered at present as a potential candidate for the coolant of new generation fast reactors(critical and subcritical) and for liquid spallation neutron sources and accelerator driven systems(ADS). A high temperature liquid LBE loop, KYLIN-II-M,has been built to study the characteristics of corrosion and fluidity of LBE at the Institute of Nuclear Energy Safety Technology. However, due to the sensors and execution components of the loop work at high temperatures and in severely corrosive environments, the reliability and security of the data acquisition and control system(DACS) of KYLIN-II-M face challenges during the loop operation. In order to meet the urgent needs for KYLIN-II-M’s long-term stable operation, a virtualization and redundancy control system has been developed.The onsite operation result shows that the DACS is stable and reliable. In this paper, the experimental results are described in detail.     

A real-time online data acquisition system for Dragon-Ⅰ linear induction accelerator

An extensible high-speed accelerator data acquisition system (ADAS) for the Dragon-Ⅰ linear induction accelerator has been developed.It comprises a ⅤⅪ crate,a controller,four data acquisition plug-ins,and a host computer.A digital compensation algorithm is used to compensate for the distortion of high-speed signals arising from longdistance transmission.Compared with the traditional oscilloscope wall,ADAS has significant improvements in system integration,automation,and reliability.It achieves unified management of data acquisition and waveform monitoring and performs excellently with a 107-ps high-accuracy trigger and 32-channel signal monitoring.In this paper,we focus on the system architecture and hardware design of the ADAS,realization of the trigger,and digital compensation algorithm.     

A VMEbus interface for multi—detector trigger and control system

MUSE（MUltiplicity SElector)is the trigger and control system of CHIMERA,a 4π charged particles detector.Initialization of MUSE can be performed via VMEbus.This paper describes the design of VMEbus interface and functional module in muse,and briefs an application of MUSE.     

Recommended decay data and evaluated databases – international perspectives

Nationally and internationally sponsored libraries of evaluated decay data are briefly described and discussed in terms of their contents. Such databases contain uniquely defined and recommended data-sets that are intended for adoption with confidence in both energy and non-energy fields of application. Example evaluations are given to demonstrate the form of methodology adopted in such work, along with the emergence of powerful software techniques to display the recommended decay data in user-friendly forms. Decay-data requirements in both nuclear power generation and nuclear medicine are also assessed ? inadequacies in the existing decay data of specific radionuclides have been identified, and are reviewed in order to define the need for further studies.     

Sorption power – a control test for impregnated carbons for nuclear power plants

A method is proposed for determining the sorption power of impregnated activated carbons used for removing the radioactive iodine from gaseous radioactive wastes at nuclear power plants. The sorption power, which is determined from the activity distribution along the sorbent layer and the residence time of the gas flow in the volume of the activated carbon, is proposed as a criterion for the sorbent’s power to catch radioactive methyl iodide.     

NXcom – A program for calculating attenuation coefficients of fast neutrons and gamma-rays

This work is concerned with a construction and use of NXcom computer program for calculating the removal and attenuation coefficients of transmitted fast neutrons and γ-rays, respectively, through mixtures, composites, concretes and compounds. The program uses only one input data file for neutrons and γ-rays calculations. For γ-ray attenuation, the program predictions were tested by comparing them with the well-known WinXcom program results and an excellent agreement was noticed. Also, it has been used for calculating the values of macroscopic effective removal cross-sections Σ_R (cm⁻¹) for five new published polyamide and anhydride composites designed for shielding mixed neutron and γ-rays. The obtained values for Σ_R using the program and the reported attenuation thicknesses which were based on the Monte Carlo N-Particle (MCNP) code showed the same trend. The NXcom program can be used as a preliminary effective tool for testing the shielding material against fast neutrons and γ-rays.     

Benchmark data for 1.43 MeV γ-rays penetrating Pb,steel, Al and graphite shields

NH₄VO₃ solution was pumped around an in-pile closed circuit to provide a uniform disc source of 1.43 MeV γ-rays from the decay of ⁵²V. Angular and scalar flux spectra are presented for 1.43 γ-rays penetrating shielding slabs of 1.54 m.f.p. Pb, 0.99 and 1.99 m.f.p. steel, 0.79, 1.40 and 2.10 m.f.p. Al and 1.38 m.f.p. of graphite. The spectra have been obtained from the unfolding of scintillation spectrometer outputs using the code radak. Such data can be used for the evaluation of calculational methods.     

Nuclear High-Spin Data for A=174, 176, and 184

Nuclear high-spin data are important in the frontier areas of nuclear structure physics. Nearly all nuclear physics groups active in high-spin research maintain a computerized data file of the level schemes deduced from their own experiments. Furthermore, several of those groups have also made an effort to produce data files for specific mass regions that address the needs of their own     

Spectral data and grotrian diagrams for highly ionized titanium,Ti V–Ti XXII

Wavelengths, energy levels, level configurations, oscillator strengths, and radiative transition probabilities for the titanium ions Ti V to Ti XXII are critically reviewed and tabulated. Grotrian diagrams are also presented to provide a graphical overview.     

Combination of resonance integral and Maxwellian 30 keV data – A sensitive test of the resonance region

This paper presents the approach of a combined use of resonance integrals and average Maxwellian cross sections (MACS) at kT = 30 keV to test and validate the resolved resonance range or its reconstructed cross section curve. Based on these two integral measurements a sensitive and energy dependent test can be provided. These two integral quantities cover with their neutron spectra the energy region between E_n = 0.5 eV up to several hundred keV, respectively, with different weighting. Our principal motivation is to produce a validation tool, sensitive to the lower and upper parts of the resonance region through the difference in the applied 1/E and kT = 30 keV Maxwell–Boltzmann spectra of the resonance integral and MACS data.     

A Decay chain Data Library for Activation Products,Fission Products and Actinides

1.Introduction A FDKR code is developed on the basis DKR to calculate the radioactivity of fusion-fission hybrid reactor.The main radioactive sources in a hybrid reactorare activation products from structural materials,actinides,and fission productsfrom fission reactions.So,a new decay chain data library(AF-DCDLIB)is compiled,     

Stopping powers of Pd,Lu and Gd for 1.0–5.0 MeV 7Li ions

Stopping powers of ⁷Li ions in Pd, Lu and Gd were measured near their maximum with experimental error less than 6%. The experimental results were compared with TRIM91 and SRIM96 predictions. The ⁴He energy loss was taken as the measure of the sample foil thickness. The effective charge ratios of ⁷Li ions to hydrogen were examined and found to be a complex function of ion energy.     

Oxidation behaviour of zirconium alloys and their precipitates – A mechanistic study

The precipitate oxidation behaviour of binary zirconium alloys containing 1 wt.% Fe, Ni, Cr or 0.6 wt.% Nb was characterised in TEM on FIB prepared transverse sections of the oxide and reported in previous studies [1], [2]. In the present study the following alloys: Zr1%Cu, Zr0.5%Cu0.5%Mo and pure Zr are analysed to add to the available information. In all cases, the observed precipitate oxidation behaviour in the oxide close to the metal-oxide interface could be described either with delayed oxidation with respect to the matrix or simultaneous oxidation as the surrounding zirconium matrix. Attempt was made to explain these observations, with different parameters such as precipitate size and structure, composition and thermodynamic properties. It was concluded that the thermodynamics with the new approach presented could explain most precisely their behaviour, considering the precipitate stoichiometry and the free energy of oxidation of the constituting elements.The surface topography of the oxidised materials, as well as the microstructure of the oxide presenting microcracks have been examined. A systematic presence of microcracks above the precipitates exhibiting delayed oxidation has been found; the height of these crack calculated using the Pilling–Bedworth ratios of different phases present, can explain their origin. The protrusions at the surface in the case of materials containing large precipitates can be unambiguously correlated to the presence of these latter, and the height can be correlated to the Pilling–Bedworth ratios of the phases present as well as the diffusion of the alloying elements to the surface and their subsequent oxidation. This latter behaviour was much more considerable in the case of Fe and Cu with Fe showing systematically diffusion to the outer surface.     

Stopping powers of C,Al, Ni,Cu, In,Sn, Ag and Au for 7Li ions of 1.0–4.7 MeV

Stopping powers for ⁷Li ions in selected target elements were determined for the energy range 2.0–4.7 MeV. This range was extended below 1.0 MeV for elements for which measurements were not available. A surface barrier detector was used to compare the energy loss of ⁷Li and ⁴He ions in thin, self-supported films. The ⁴He energy loss was taken as the measure of the film thickness. An energy dependence was confirmed for the ratio of the effective charges of lithium to hydrogen ions at the same velocity.     

Mechanisms of DNA Damage and Repair Implications for Carcinogenesis and Risk Assessment June 2-7, 1985 DNA is the Beginning and the End

Program Sessions Monday,June 3,19859:00 a.m.-WelcomeIntroduction.Sanford A.Miller,Ph.D.,Director Center for Food Safety and Applied Nutrition Food and Drug Administration,Washington, D.C..David P.Rall,M.D.,Ph.D.Director National Institute of Environmental Health     

A simple method for estimating the structure temperatures and the cesium revaporization inside the reactor pressure vessel – I: Basic concepts and model descriptions for the Fukushima Daiichi Nuclear Power Plant

This paper presents a simple approach for estimating the structure temperatures including the uncovered reactor core inside the reactor pressure vessel (RPV) and the release rates of fission products deposited in the RPV to the reactor building (R/B) at a certain time after the occurrence of a severe accident at a nuclear power plant (NPP). First, basic concepts are presented and then, a simplified steady-state heat balance model is proposed for estimating the temperatures of the uncovered reactor core and the upper structure in the RPV as well as the temperature of the RPV wall. In addition, models for estimating the revaporization rate of cesium hydroxide (CsOH) in the RPV and the leak rate of CsOH to the R/B via the drywell are also presented. The proposed approach is anticipated to be applicable to the damaged Units 1–3 of the Fukushima Daiichi NPP.