MCNP5在固态燃料熔盐堆功率分布计算的应用

采用蒙特卡罗输运程序MCNP5对固态燃料熔盐实验堆(TMSR-SF1)能量沉积比例及功率分布进行了计算分析。针对MCNP5不能处理缓发β及缓发γ的能量沉积问题进行了类比等效处理。对固态燃料熔盐实验堆在寿期初、寿期中、寿期末相应的能量沉积比例及功率分布进行了研究。通过计算发现,固态燃料熔盐实验堆内燃料球相比于压水堆棒状燃料元件(95%~97%左右)而言,能量沉积比例有所偏小,约为93%。同时,由于堆芯功率分布均匀,功率峰因子较小(约1.5),堆芯安全性较好。     

新型钍基熔盐堆多物理计算模型及分析

针对熔盐堆系统特点,提出了包含堆芯及其他主回路系统在内的多物理紧密耦合计算模型,并在此基础上自主开发了多物理分析程序TANG-MSR。利用该程序进行了新型钍基熔盐堆(TMSR)的设计,并对设计方案进行了稳态及瞬态分析。相关计算结果表明,TANG-MSR所采用的多物理模型能够很好地捕捉熔盐堆的主要物理现象,提出的新型熔盐堆设计在安全性和可持续性方面表现优异。关键词:多物理模型;新型钍基熔盐堆;稳态;瞬态 Abstract: Key words:     

新型钍基熔盐堆多物理计算模型及分析

针对熔盐堆系统特点,提出了包含堆芯及其他主回路系统在内的多物理紧密耦合计算模型,并在此基础上自主开发了多物理分析程序TANG-MSR。利用该程序进行了新型钍基熔盐堆(TMSR)的设计,并对设计方案进行了稳态及瞬态分析。相关计算结果表明,TANG-MSR所采用的多物理模型能够很好地捕捉熔盐堆的主要物理现象,提出的新型熔盐堆设计在安全性和可持续性方面表现优异。关键词：多物理模型;新型钍基熔盐堆;稳态;瞬态 Abstract: Key words:     

Steady state investigation on neutronics of a molten salt reactor considering the flow effect of fuel salt

The Molten Salt Reactor (MSR), one of the `Generation IV' concepts, is a liquid-fuel reactor, which is different from the conventional reactors using solid fissile materials due to the flow effect of fuel salt. The study on its neutronics considering the fuel salt flow, which is the base of the thermal-hydraulic calculation and safety analysis, must be done. In this paper, the theoretical model on neutronics under steady condition for a single-liquid-fueled MSR is conducted and calculated by numerical method. The neutronics model consists of two group neutron diffusion equations for fast and thermal neutron fluxes, and balance equations for six-group delayed neutron precursors considering the flow effect of fuel salt. The spatial discretization of the above models is based on the finite volume method, and the discretization equations are computed by the source iteration method. The distributions of neutron fluxes and the distributions of the delayed neutron precursors in the core are obtained. The numerical calculated results show that, the fuel salt flow has little effect on the distribution of fast and thermal neutron fluxes and the effective multiplication factor; however, it affects the distribution of the delayed neutron precursors significantly, especially the long-lived one. In addition, it could be found that the delayed neutron precursors influence the neutronics slightly under the steady condition.     

Steady state investigation on neutronics of a molten salt reactor considering the flow effect of fuel salt

The Molten Salt Reactor (MSR),one of the‘Generation Ⅳ'concepts,is a liquid-fuel reactor,which is different from the conventional reactors using solid fissile materials due to the flow effect of fuel salt.The study on its neutronice considering the fuel salt flow,which is the base of the thermal-hydraulic calculation and safety analysis,must be done.In this paper,the theoretical model on neutronics under steady condition for a single-liquid-fueled MSR is conducted and calculated by numerical method.The neutronics model consists of two group neutron diffusion equations for fast and thermal neutron fluxes,and balance equations for six-group delayed neutron precursors considering the flow effect of fuel salt. The spatial discretization of the above models is based on the finite volume method,and the discretization equations are computed by the source iteration method.The distributions of neutron fluxes and the distributions of the delayed neutron precursors in the core are obtained.The numerical calculated results show that,the fuel salt flow has little effect on the distribution of fast and thermal neutron fluxes and the effective multiplication factor;however,it affects the distribution of the delayed neutron precursors significantly,especially the long-lived one.In addition,it could be found that the delayed neutron precursors influence the nentronics slightly under the steady condition.     

新型钍基熔盐堆堆芯方案及燃耗分析

采用自主开发的SONG/TANG-MSR栅格/堆芯分析程序对新型钍基熔盐堆（TMSR）进行堆芯布置与燃耗分析计算。根据前期的栅格分析相关工作,TMSR采用了无铍（BeF2）燃料熔盐、氧化铍慢化剂以及碳化硅包壳,并在组件栅格初步优化分析的基础上,通过全堆芯计算对熔盐栅格进一步优化和分析,给出了堆芯三区布置方案。该方案具有较高的增殖比,负的功率系数,以及较平的温度分布。根据该堆芯方案,在考虑熔盐在线处理情况下进行了熔盐燃耗计算分析。结果表明,堆芯具有较高的增殖比、较短的倍增时间以及长期稳定运行能力。新型的钍基熔盐设计大大提高了增殖性能,同时又确保堆芯具有足够的安全性能。     

新型钍基熔盐堆堆芯方案及燃耗分析

采用自主开发的SONG/TANG-MSR栅格/堆芯分析程序对新型钍基熔盐堆（TMSR）进行堆芯布置与燃耗分析计算。根据前期的栅格分析相关工作,TMSR采用了无铍（BeF2）燃料熔盐、氧化铍慢化剂以及碳化硅包壳,并在组件栅格初步优化分析的基础上,通过全堆芯计算对熔盐栅格进一步优化和分析,给出了堆芯三区布置方案。该方案具有较高的增殖比,负的功率系数,以及较平的温度分布。根据该堆芯方案,在考虑熔盐在线处理情况下进行了熔盐燃耗计算分析。结果表明,堆芯具有较高的增殖比、较短的倍增时间以及长期稳定运行能力。新型的钍基熔盐设计大大提高了增殖性能,同时又确保堆芯具有足够的安全性能。     

Prediction of the thermophysical properties of molten salt fast reactor fuel from first-principles

Molten fluorides are known to show favourable thermophysical properties which make them good candidate coolants for nuclear fission reactors. Here we investigate the special case of mixtures of lithium fluoride and thorium fluoride, which act both as coolant and as fuel in the molten salt fast reactor concept. By using ab initio parameterised polarisable force fields, we show that it is possible to calculate the whole set of properties (density, thermal expansion, heat capacity, viscosity and thermal conductivity) which are necessary for assessing the heat transfer performance of the melt over the whole range of compositions and temperatures. We then deduce from our calculations several figures of merit which are important in helping the optimisation of the design of molten salt fast reactors.     

钍基熔盐堆新型栅格设计与优化

利用上海核工院自主开发的SONG/TANG-MSR程序系统,通过大量的方案筛选,在熔盐燃料成分、慢化剂材料以及栅格结构等方面对钍基熔盐堆（TMSR）栅格进行设计优化。提出采用无铍熔盐作为燃料,以提高重核（ThF4, UF4）溶解度;采用氧化铍（BeO）作为慢化剂,从而提高中子经济性;创新性地采用熔盐燃料与慢化剂隔离的SiC包壳管设计,保持堆芯结构的稳定性和抗辐照性能。对优化后的栅格设计计算结果表明:新型的熔盐堆栅格设计具有很高的增殖比并保持负功率系数,从而满足下一代核能系统可持续性和安全性要求。     

钍基熔盐堆新型栅格设计与优化

利用上海核工院自主开发的SONG/TANG-MSR程序系统,通过大量的方案筛选,在熔盐燃料成分、慢化剂材料以及栅格结构等方面对钍基熔盐堆（TMSR）栅格进行设计优化。提出采用无铍熔盐作为燃料,以提高重核（ThF4, UF4）溶解度;采用氧化铍（BeO）作为慢化剂,从而提高中子经济性;创新性地采用熔盐燃料与慢化剂隔离的SiC包壳管设计,保持堆芯结构的稳定性和抗辐照性能。对优化后的栅格设计计算结果表明:新型的熔盐堆栅格设计具有很高的增殖比并保持负功率系数,从而满足下一代核能系统可持续性和安全性要求。     

The BURNUP package of applied programs used for computing the isotopic composition of materials of an operating nuclear reactor

This paper described the procedure of implementation and the possibilities of the BURNUP program. The purpose of the program is to predict the change in the nuclear composition of the materials of which a reactor is made in the course of its run and compute the radiation characteristics of the materials after their irradiation.     

Dielectric and transport properties of a supercooled symmetrical molten salt

The liquid-glass transition of the restricted primitive model for a symmetrical molten salt is studied using mode-coupling theory. The transition at high densities is predicted to obey the Lindemann criterion for melting, and the charge-density peak found in neutron-scattering experiments on ionic glass formers is qualitatively reproduced. Frequency-dependent dielectric functions, shear viscosities, and dynamical conductivities of the supercooled liquid are presented. Comparing the latter to the diffusion constant, we find that mode-coupling theory reproduces the Nernst-Einstein relation. The Stokes-Einstein radius is found to be approximately equal to the particle radius only near the high-density glass transition.     

The use of linear superconducting electron accelerator for subcritical reactor driving

At the National Science Centre, Kharkiv Institute of Physics and Technology (NSC KIPT) the possibility of creating an installation with a subcritical reactor driven by an electron accelerator is examined. To obtain the maximal stream of neutrons from a neutron-producing target at a minimal density of energy emission, the electron energy should be in the range of 100–200 MeV and the size of the target should be as large as possible. Other important requirements are beam continuity with time and long-term stability of the accelerator parameters. The variants of using the superconducting linear accelerator on the basis of a TESLA accelerating structure as of subcritical reactor driver are considered. The basic design parameters and characteristics of this installation are presented. The text was submitted by the authors in English.     

AgF desalination procedure for the routine determination of oxygen and hydrogen isotopic composition of saline waters and brines

The routine methods for stable oxygen and hydrogen isotope analysis of water involve water–CO₂ gas equilibration and water reduction on hot metal (e.g. Zn, Cr, U) and subsequent mass spectrometric analysis of the evolved gases of CO₂ and H₂ for ¹⁸O/¹⁶O and ²H/¹H ratios, respectively. Precise determination of the isotopic composition of water in brines with application of these standard methods is still problematic and technically often impossible due to detrimental influence of dissolved salts. The new method of brine desalination presented in this study overcomes the problem of the isotope salt effects encountered during the application of the routine techniques for the determination of the isotopic composition of high saline waters. The procedure combines two technical steps: (i) the chemical precipitation of Mg and Ca ions as insoluble non-hydroscopic fluorides, and (ii) the vacuum distillation of water from solution–precipitate mixture. The application of simple vacuum distillation allows full extraction of water and dehydration of remaining salts in a temperature range from 300 to 350?°C without hydrogen and oxygen isotope fractionation. The precision and accuracy of δ¹⁸O and δ²H determination of saline waters and brines with prior application of AgF desalination procedure is comparable with that usually obtained for fresh waters.     

HNC calculations of the partial structure factors of molten AgI

We have calculated the pair distribution functions and partial structure factors of molten AgI within the hypernetted chain (HNC) approximation. We have assumed that the effective interionic pair potentials are the same in the liquid and solid states, and have used the potentials constructed by Parrinello et al., which they used to describe both -AgI and the phase transition in AgI. The structure of molten AgI exhibits features similar to those of molten CuCl. Both of these salts melts from a superionic phase.     

The isotopic composition of palladium in meteorites and terrestrial samples

The isotopic composition of palladium has been measured in a range of terrestrial and meteoritic material using solid-source mass spectrometry. Within the limits of experimental error the isotopic composition of palladium was found to be uniform in all terrestrial samples, except a precious metal concentrate from South Africa, in which it was isotopically fractionated by 3.8% per mass unit with the enrichment in the heavy isotopes. This places a limit of 1 part in 10⁴ on the accuracy to which the atomic weight of terrestrial palladium can be known. Apart from linear fractionation effects, the measured isotope abundances are in excellent agreement with the work of Shima et al. [14] and Kelly and Wasserburg [15]. Isotopic data from a selection of iron and stone meteorite samples did not reveal any evidence of inhomogeneous mixing of r- and s-process nuclides. If r-process material has been added to the meteorites, it must constitute less than 0.3% of the palladium present.     

Parallelization of heterogeneous reactor calculations on a graphics processing unit

Parallelization is applied to the neutron calculations performed by the heterogeneous method on a graphics processing unit. The parallel algorithm of the modified TREC code is described. The efficiency of the parallel algorithm is evaluated.