Operation of CANDU power reactor in thorium self-sufficient fuel cycle

This paper presents the results of calculations for CANDU reactor operation in thorium fuel cycle. Calculations are performed to estimate the feasibility of operation of heavy-water thermal neutron power reactor in self-sufficient thorium cycle. Parameters of active core and scheme of fuel reloading were considered to be the same as for standard operation in uranium cycle. Two modes of operations are discussed in the paper: mode of preliminary accumulation of ²³³U and mode of operation in self-sufficient cycle. For the mode of accumulation of ²³³U it was assumed for calculations that plutonium can be used as additional fissile material to provide neutrons for ²³³U production. Plutonium was placed in fuel channels, while ²³²Th was located in target channels. Maximum content of ²³³U in target channels was estimated to be ∼13 kg/t of ThO₂. This was achieved by irradiation for six years. The start of the reactor operation in the self-sufficient mode requires ²³³U content to be not less than 12 kg/t. For the mode of operation in self-sufficient cycle, it was assumed that all channels were loaded with identical fuel assemblies containing ThO₂ and certain amount of ²³³U. It is shown that nonuniform distribution of ²³³U in fuel assembly is preferable.      

An EDXRF method for determination of uranium and thorium in AHWR fuel after dissolution

A fast energy dispersive x‐ray fluorescence (EDXRF) method requiring only microgram amounts of analytes, i.e. uranium (U) and thorium (Th), in their mixtures in solution form is described. Calibration solutions and samples covering the fuel composition range (0–5% of U in U + Th) of advanced heavy water reactor (AHWR) were prepared by mixing uranium and thorium solutions. A known fixed amount of internal standard yttrium (Y) was added to these solutions. EDXRF spectra of calibration solutions and samples were measured by taking 20 µl aliquots on 30 mm diameter filter papers, after drying, using a Rh target tube operated at 40 kV and 500 µA. Calibration plots were made by plotting U/Y, U/Th and Th/Y amount ratios against the respective intensity ratios of Th Lα, U Lα and Y Kα. In the first set, U was determined using Y as an internal standard, and for Th determination, U, thus determined, was used as an internal standard since the amounts of Th and Y were kept constant in the calibration solutions and samples. In the second set, both U and Th were varied and determined using Y as internal standard. The results of U and Th determinations showed a precision of about 3% (1s) and the results deviated from the expected values by <3% in most of the cases. This approach has an advantage that it requires only microgram amounts of sample, thus mitigating radiation hazards associated with radioactive samples as well as the amount of radioactive analytical waste generated is quite less. Copyright © 2009 John Wiley & Sons, Ltd.     

钠冷快堆及其安全特性

钠冷快堆是第四代核能系统国际论坛(GIF)公布的6种第四代先进反应堆中研发进展最快、最接近满足商业核电厂需要的堆型。钠冷快堆因其在固有安全性以及可增殖核燃料、嬗变长寿命放射性废物等方面的优势,得到了世界各国的重视。文章以中国第一座钠冷快堆——中国实验快堆(China Experimental Fast Reactor,CEFR)为例,介绍了钠冷快堆在设计及运行方面的安全特性。     

Unified treatment for accurate and fast evaluation of the Fermi-Dirac functions

A new analytical approach to the computation of the Fermi-Dirac(FD) functions is presented,which was suggested by previous experience with various algorithms.Using the binomial expansion theorem,these functions are expressed through the binomial coefficients and familiar incomplete Gamma functions.This simplification and the use of the memory of the computer for the calculation of binomial coefficients may extend the limits to large arguments for users and result in speedier calculation,should such limits be required in practice.Some numerical results are presented for significant mapping examples and they are briefly discussed.     

Multiple recycling of fuel in prototype fast breeder reactor

In a thermal neutron reactor, multiple recycle of U-Pu fuel is not possible due to degradation of fissile content of Pu in just one recycle. In the FBR closed fuel cycle, possibility of multi-recycle has been recognized. In the present study, Pu-239 equivalence approach is used to demonstrate the feasibility of achieving near constant input inventory of Pu and near stable Pu isotopic composition after a few recycles of the same fuel of the prototype fast breeder reactor under construction at Kalpakkam. After about five recycles, the cycle-to-cycle variation in the above parameters is below 1%.      

一种用于中子散射成像的快速反投影重建方法

针对中子散射成像建立了一种快速反投影重建方法,这种方法首先根据每一个散射事件确定粒子可能所在的空间范围,然后该空间范围中进行重建,大大减少了重建的运行时间。应用所建立的方法对模拟的成像数据进行处理,结果表明:重建源与实际源的位向一致,对1000个散射数据进行处理,用时约3 s;对5探测单元成像得到的模拟数据处理,得到重建后点源的位向分辨为8.0°;重建源的位向分辨不随设定重建平面的位置而改变,但重建平面距探测平面越近,重建速度越快;当重建平面达到一定尺寸时,继续增加大重建平面尺寸,重建的运行时间增加不明显,该方法在大视场空间探测成像应用中,具有较高的重建效率。     

一种用于中子散射成像的快速反投影重建方法

针对中子散射成像建立了一种快速反投影重建方法,这种方法首先根据每一个散射事件确定粒子可能所在的空间范围,然后该空间范围中进行重建,大大减少了重建的运行时间。应用所建立的方法对模拟的成像数据进行处理,结果表明：重建源与实际源的位向一致,对1000个散射数据进行处理,用时约3 s;对5探测单元成像得到的模拟数据处理,得到重建后点源的位向分辨为8.0;重建源的位向分辨不随设定重建平面的位置而改变,但重建平面距探测平面越近,重建速度越快;当重建平面达到一定尺寸时,继续增加大重建平面尺寸,重建的运行时间增加不明显,该方法在大视场空间探测成像应用中,具有较高的重建效率。     

A capture-gated fast neutron detection method

To address the problem of the shortage of neutron detectors used in radiation portal monitors(RPMs),caused by the ~3He supply crisis, research on a cadmium-based capture-gated fast neutron detector is presented in this paper. The detector is composed of many 1 cm × 1 cm × 20 cm plastic scintillator cuboids covered by 0.1 mm thick film of cadmium. The detector uses cadmium to absorb thermal neutrons and produce capture γ-rays to indicate the detection of neutrons, and uses plastic scintillator to moderate neutrons and register γ-rays. This design removes the volume competing relationship in traditional ~3He counter-based fast neutron detectors, which hinders enhancement of the neutron detection efficiency. Detection efficiency of 21.66% ± 1.22% has been achieved with a 40.4 cm × 40.4cm × 20 cm overall detector volume. This detector can measure both neutrons and γ-rays simultaneously. A small detector(20.2 cm × 20.2 cm × 20 cm) demonstrated a 3.3 % false alarm rate for a ~(252)Cf source with a neutron yield of 1841 n/s from 50 cm away within 15 s measurement time. It also demonstrated a very low(0.06%) false alarm rate for a 3.21 × 10~5 Bq ~(137)Cs source. This detector offers a potential single-detector replacement for both neutron and the γ-ray detectors in RPM systems.     

快Z箍缩钨丝阵内爆物理研究

通过理论和实验研究了快Z箍缩电磁内爆动力学物理过程及其辐射特性,完成了1维和2维辐射磁流体动力学数值模拟程序。利用阳加速器、强光一号脉冲功率装置、S-300装置和Angara-5-1装置,开展了实验研究,发展了一系列观察Z箍缩等离子体辐射的诊断系统。研制了单层、双层钨丝阵及单层丝阵加聚氘乙烯芯等负载。重点研究了能量耦合和内爆动力学规律。     

Ceramics for fusion reactors: The role of the lithium orthosilicate as breeder

Lithium-based oxide ceramics are studied as breeder blanket materials for the controlled thermonuclear reactors (CTR). Lithium orthosilicate (Li₄SiO₄) is one of the most promising candidates because of its lithium concentration (0.54 g/cm³), its high melting temperature (1523 K) and its excellent tritium release behavior. It is reported that the diffusion of tritium is closely related to that of lithium, so it is possible to find an indirect measure of the trend of tritium studying the diffusivity of Li⁺.     

Neutronic calculations for CANDU thorium systems using Monte Carlo techniques

In this paper,we have investigated the prospects of exploiting the rich world thorium reserves using Canada Deuterium Uranium(CANDU)reactors.The analysis is performed using the Monte Carlo MCNP code in order to understand how much time the reactor is in criticality conduction.Four different fuel compositions have been selected for analysis.We have obtained the infinite multiplication factor,k∞,under full power operation of the reactor over 8 years.The neutronic flux distribution in the full core reactor has already been investigated.     

Neutronic calculations for CANDU thorium systems using Monte Carlo techniques

In this paper, we have investigated the prospects of exploiting the rich world thorium reserves using Canada Deuterium Uranium （CANDU） reactors. The analysis is performed using the Monte Carlo MCNP code in order to understand how much time the reactor is in criticality conduction. Four different fuel compositions have been selected for analysis. We have obtained the infinite multiplication factor, k∞, under full power operation of the reactor over 8 years. The neutronic flux distribution in the full core reactor has already been investigated.     

The physics of accelerator driven sub-critical reactors

In recent years, there has been an increasing worldwide interest in accelerator driven systems (ADS) due to their perceived superior safety characteristics and their potential for burning actinides and long-lived fission products. Indian interest in ADS has an additional dimension, which is related to our planned large-scale thorium utilization for future nuclear energy generation. The physics of ADS is quite different from that of critical reactors. As such, physics studies on ADS reactors are necessary for gaining an understanding of these systems. Development of theoretical tools and experimental facilities for studying the physics of ADS reactors constitute important aspect of the ADS development program at BARC. This includes computer codes for burnup studies based on transport theory and Monte Carlo methods, codes for studying the kinetics of ADS and sub-critical facilities driven by 14 MeV neutron generators for ADS experiments and development of sub-criticality measurement methods. The paper discusses the physics issues specific to ADS reactors and presents the status of the reactor physics program and some of the ADS concepts under study.      

超快中子探测器闪烁体性能计算

超快中子探测器是ICF聚变反应速率测量系统的核心部件。利用蒙特卡罗粒子输运工具包Geant4模拟了一种超快中子探测器——BC-422型闪烁探测器的中子探测过程,计算出了几种厚度的BC-422型闪烁体的探测效率、输出光信号强度和时间分辨力;对比了闪烁体的2种不同反射表面对输出光信号强度和时间分辨力的影响。计算的结果显示：设计适当的BC 422型闪烁探测器能够测量的最低中子产额在108量级,对DT中子的信号时间分辨力好于20 ps,对DD中子的信号时间分辨力达到30 ps,能够用于大型激光装置及其原型的聚变反应速率测量。     

Analysis and design considerations for a real-time system for non-destructive evaluation in the nuclear industry

This paper studies the feasibility of implementing a real-time system for non-destructive evaluation of nuclear reactors based on the principles of synthetic aperture processing. A detailed analysis of the computational requirements and simulation and benchmarking work on several computers seems to suggest the design of a special purpose processor as the most viable solution to the problem. The paper concludes with a discussion of the parameters affecting field design and some preliminary design considerations of the overall system.     

Bedeutung und Stand verfahrenstechnischer Untersuchungen mit Radionukliden in der chemischen Industrie Zusammenfassender Bericht

Die Anwendung radioaktiver Nuklide in der chemischen Industrie kann nach der jeweils verwendeten Eigenschaft des strahlenden Materials in drei Gruppen eingeordnet werden     

Contribution of different mechanisms of energy transfer in the development of the thermonuclear combustion wave upon fast ignition of ICF-targets

Temporal characteristics of the thermonuclear combustion wave, critical parameters of the igniter, and the total energy yield were computed using numerical modeling of the fast ignition of the spherically symmetric inertial confinement fusion (ICF) target of the reactor type taking into account different mechanisms of energy transfer from the central igniter to the main mass of fusionable fuel of the target. The program TERA was used for mathematical modeling. Along with complete calculations (including all known mechanisms of energy transfer), model computations with consecutive disengagement of energy transfer by thermonuclear charged particles (local energy deposition approximation) and by neutrons were also carried out. Our computations showed that the main effect consists in variation of the temporal characteristics of the combustion wave. Unlike the diagnostic-type targets, in the case of the reactor targets, energy transfer by neutrons exerts the main influence, and the second in importance is nonlocality of the energy deposition by charged thermonuclear particles.