863计划聚变－裂变混合堆专题研究取得重大进展

８６３计划聚变－裂变混合堆专题研究取得重大进展多发弹丸固体加料注入技术实验研究是国家八六三计划能源领域聚变一裂变混合堆专题的研究课题之一，研究目标是在“七五”研制成功单发弹丸注入系统并实现单发弹丸注入的基础上，研制成功多发弹丸注入系统并完成多发弹丸注...     

聚变－裂变混合堆专题高功率低混杂波电流驱动实验获得成功

聚变－裂变混合堆专题高功率低混杂波电流驱动实验获得成功８６３计划聚变－裂变混合堆专题高功率低混杂波电流驱动实验近期获得成功。低混杂波电流驱动（ＬＨＣＤ）是维持托卡马克聚变堆稳态运行最有效的方法之一，也是改善和提高加热功率的一项关键技术，世界各先进国家...     

裂变核能源持续发展的条件和可能

提出了裂变核和可转化核混合燃料成分的平衡点的概念,分析了利用燃料成分平衡点设计反应堆,以适应核裂变能源持续发展需要的可能性。     

高放废物中^238Pu,^240Pu,^242Pu在聚变—裂变混合堆内的嬗变研究

从中子学角度研究了高放废物中２３８Ｐｕ、２４０Ｐｕ、２４２Ｐｕ在聚变一裂变混合堆内擅变的可行性。选取２３３Ｕ做中子增殖剂，对四个不同燃料组分的快谱包层进行了设计，利用输运一燃耗程序ＢＩＤＥＡＹ对所选方案进行了计算分析，结果表明：用２３３Ｕ做中子增殖剂，在聚变一裂变混合堆快谱包层内擅变２３８Ｐｕ、２４０Ｐｕ、２４２Ｐｕ是安全可行的。     

在线产氚回路及其在混合堆包层研究中的应用

介绍了我国第一条反应堆在线产氚回路，说明了回路的组成及其主要技术指标，叙述了回路的运行概况和放氚实验的结论，讨论了在线产氚回路在聚变－裂变混合堆包层产氚研究中的应用及前景。     

核能技术方向研究及发展路线图

笔者按照核能技术成熟度将课题分解为热堆、快堆和四代堆、受控核聚变科学技术三个专题,采取专题调研、交叉讨论、系统综合的方法开展研究。分析了核能技术发展的现状、我国核能的安全性、核能技术的发展方向,并给出了核能技术发展路线图。建议以第三代自主压水堆为依托,安全、高效、规模化发展核能;加快第四代核能系统研发,解决核燃料增殖与高水平放射性核素嬗变;积极发展模块化小堆,开拓核能应用范围;努力探索聚变能源。预期到2030年核电运行1.5×10~8 kW,在建5×10~7 kW;到2050年快堆和压水堆匹配发展。我国核能发展存在前端和后端能力不足、核心技术研发力量分散、竞争大于合作的局面,建议整合国内资源,组建核能国家实验室,集中力量推进我国核能产业健康、快速发展。     

我国基于快堆的可持续核能系统发展思考

核能是优化我国能源结构,降低二氧化碳排放的重要能源形式之一。近期我国的核能仍然将以压水堆为主,但压水堆的长期发展将带来铀资源缺乏和放射性废物处置的问题。研究表明基于快堆的闭式燃料循环可通过多次的循环有效增殖核燃料,同时具备嬗变6座以上同等规模压水堆产生的锕系核素(MA)的能力。根据我国快堆"实验堆–示范堆–商用堆"三阶段发展战略,同时结合我国核电起步较晚的国情,建议在2050年之前主要实施快堆增殖核燃料,在2050年之后实施MA嬗变的技术路线。     

固体氚增殖剂的制备及性能综述

聚变或聚变一裂变混合堆中通常采用含锂的材料作为氚增殖剂.概述并比较了氚增殖剂的几种制备方法,就几种氚增殖剂的热学、化学、机械性能、辐照行为和氚释放等进行了综合评述,简单介绍了氚增殖剂在聚变堆中的作用和发展趋势,为我国实验包层模块(TBM)产氚包层中氚增殖剂的深入研究奠定了基础.     

水裂变的机理的探讨

水在超高温条件下可以裂变生成氢气,美科学家似已认定,澳新式太阳能发电提高26%发电功率似给予了证实。本文论述水在超高温条件下裂变生成氢气的机理及澳新式太阳能发电提高26%发电功率的原因。水在超高温条件下分子内的氢、氧原子急速转动产生的离心力≧向心力时,氢、氧原子间的氢键自然断裂,氢、氧原子变成——氢和氧。氢遇火燃烧放出热量生成水。水裂变热值是15888.87kj/kg,是标准煤热值的0.54217倍。就是1吨水裂变生成的氢燃烧放出的热量等于0.54217吨标准煤完全燃烧放出的热量,且为零排放。     

聚变堆结构材料辐照性能的评价

针对聚变堆特定的辐照条件,对离子辐照、裂变中子辐照、散裂中子辐照以及聚变辐照装置进行了比较,评述了不同装置的优势和缺点。在没有可用的14MeV中子源时,离子加速器、裂变堆、散裂中子源以及理论模拟在聚变材料辐照效应的研究中具有不可替代的作用。从离子辐照、裂变中子或散裂中子辐照获得的数据与真实聚变中子辐照结果的对应关系需要通过采用14MeV高通量中子辐照(如IFMIF)来证实。功能强大、经济性好的聚变材料辐照装置的建立及多尺度数值模拟的发展是聚变材料走向聚变堆应用的必由之路。     

致力项目开发点燃发展引擎——多种核能与核技术新项目开发概要

作为中国核工程开发海外市场的旗舰,中原对外工程有限公司将项目开发作为发展引擎,在百万千瓦级核电项目开发、研究性核反应堆项目开发、多功能医院中子照射器开发研究及多用途模块式小型反应堆项目开发工作中不懈努力,为和平利用核能、核技术做出贡献.     

轻水反应堆（LWR）用包壳材料研究进展

轻水反应堆（LWR）是国际上多数核电站采用的堆型。锆具有良好的加工性能,优良的机械性能,较高的熔点、优异的耐蚀性能及核性能,被用作燃料包壳和堆芯结构材料,是发展核电及核动力舰船不可替代的关键结构材料和功能材料。随着核电技术的发展,对堆芯包壳材料性能提出了更高的要求,综述了核用锆合金包壳材料的国内外研究和使用现状以及新型SiC包壳材料的研发现状。总体来说,锆合金在未来几十年内仍是核反应堆包壳材料的主要用材,开展新合金的研发,不断提升锆合金的性能是世界各国研究者共同的目标;适时加大投入力度,强化条件建设,就能加快具有国内自主知识产权锆合金的产业化步伐,可最终实现核电及核动力用锆合金材料的自主化;SiC材料具有更高的熔点、更好的耐腐蚀性能,是一种极具应用潜力的材料,有可能成为第4代核反应堆的包壳材料,但还需投入大量研究。     

惯性约束聚变／裂变混合堆核能系统的概念研究

在惯性约束聚变尚未达到能量得失相当的条件下，以惯性约束聚变产生的中子作为驱动源，￣（２３８）Ｕ或￣（２３９）Ｐｕ与￣（２３８）Ｕ的混合物作为包层核燃料，进行了聚变裂变混合放能系统的概念研究。提出了以少量￣（２３９）Ｐｕ作为“助燃剂”，用以提高包层能量倍增的概念。￣（２３９）Ｐｕ的引入提高了包层的通量水平，加速了￣（２３８）Ｕ的造钚和钚的燃烧过程，实现了消耗￣（２３８）Ｕ释放能量而不消耗或很少消耗￣（２３９）Ｐｕ，并使包层能量倍增达到３０以上，从而为惯性约束聚变的早期应用和以￣（２３８）Ｕ为裂变能源燃料的持续发展提出了一条可能的途径。     

核电先进堆型与我国核电发展

介绍了核电堆型发展的四个阶段和第一、二代核电堆型的发展历史；论述了第三代先进堆型的发展、设计特点和第四代先进堆的开发目标     

Computational Tools for the Integrated Design of Advanced Nuclear Reactors

Advanced nuclear reactors offer safe, clean, and reliable energy at the global scale. The development of such devices relies heavily upon computational models, from the pre-conceptual stages through detailed design, licensing, and operation. An integrated reactor modeling framework that enables seamless communication, coupling, automation, and continuous development brings significant new capabilities and efficiencies to the practice of reactor design. In such a system, key performance metrics (e.g., optimal fuel management, peak cladding temperature in design-basis accidents, levelized cost of electricity) can be explicitly linked to design inputs (e.g., assembly duct thickness, tolerances), enabling an exceptional level of design consistency. Coupled with high-performance computing, thousands of integrated cases can be executed simultaneously to analyze the full system, perform complete sensitivity studies, and efficiently and robustly evaluate various design tradeoffs. TerraPower has developed such a tool—the Advanced Reactor Modeling Interface (ARMI) code system—and has deployed it to support the TerraPower Traveling Wave Reactor design and other innovative energy products currently under development. The ARMI code system employs pre-existing tools with strong pedigrees alongside many new physics and data management modules necessary for innovative design. Verification and validation against previous and new physical measurements, which remain an essential element of any sound design, are being carried out. This paper summarizes the integrated core engineering tools and practices in production at TerraPower.     

SCWR for Future LargeScale Nuclear Power Generation

The ambitious nuclear power program motivates the Chinese nuclear community to develop advanced reactor concepts of generation IV, in order to ensure the longterm, stable and sustainable development of nuclear power. The supercritical watercooled reactor (SCWR) has favorable features in economics, sustainability and technology availability. It is the logical extension of the existing PWR technology and has very promising perspectives in largescale power generation in China. This paper describes the main features of SCWR. New designs of SCWR core structure and fuel assemblies are proposed. Preliminary analysis using a coupled neutronphysics/thermalhydraulics method is carried out and shows a good feasibility of the new design proposal.     

干式空心电抗器模型结构减震控制试验及数值分析

基于压电陶瓷驱动器的工作原理以及形状记忆合金(shape memory alloy,SMA)丝的力学性能特点,研发一种SMA压电混合减震装置,对其进行电-力学试验,并在试验数据的基础上建立以速率符号、电压和位移为神经元输入的混合装置BP网络预测模型。最后将其安装到一个相似比1∶2的10 kV干式空心电抗器结构模型中,其中压电驱动器的激励电压采用T-S模糊逻辑输出,对其进行无控、被动控制和混合控制时的模拟地震振动台试验和数值模拟,进而分析模型结构的动力特性变化规律和不同地震波时的地震响应抑制效果。结果表明:文中研制的SMA-压电摩擦混合减震装置性能稳定、构造合理,可以有效地降低电抗器结构的动力反应。一般地,被动控制时位移和加速度的减震率可达40%,混合控制时可达50%,且震后未见电抗器结构薄弱部位发生地震破坏,说明智能材料减震系统提高了电抗器结构的抗震可靠性,为电气设备系统的减震控制保护提供了新途径。另外,试验与数值模拟结果吻合较好,表明BP神经网络可以较好地跟踪压电SMA混合减震装置的输出力。     

事故工况下医院中子照射器I型堆瞬态特性研究

采用RELAPS/SCDAP/MOD3.4程序对医院中子照射器Ⅰ型堆(IHNI-1)在事故工况下的瞬态特性进行研究,对意外大反应性引入和池水丧失事故工况进行了计算和分析,计算结果表明:IHNI-1堆具有良好的固有安全性,在发生大反应性引入和池水丧失事故时,最终能够稳定在较低功率,确保反应堆安全.     

Morphological study of the granules in UASB and hybrid reactors

Morphology of the granules formed in anaerobic digestion of distillery wastewater was studied in two laboratory scale bioreactors i.e., upflow anaerobic sludge blanket reactor and hybrid reactor. The effects of two different inoculum sludges in early granulation and start-up were studied. Study revealed that earlier start-up and granulation of biomass could be achieved using mixed sludge (anaerobic digested sludge: cowdung and aerobic sludge) than anaerobically digested sludge. Scanning electron microscope (SEM) study of the granules showed predominance of Methanosarcina and Methanothrix type of species on the surface of granules. The change in the morphology and other physical parameters of the granules due to increase in organic loading rate were also studied. The size distribution of granules across the height of the sludge bed showed that the granules of larger diameter having higher settling velocity are mainly concentrated at the lower active zones while smaller sized granules having less settling velocity were found at the top and middle zones of the sludge bed.     

Anaerobic biogranulation in a hybrid reactor treating phenolic waste

Granulation was examined in four similar anaerobic hybrid reactors 15.5L volume (with an effective volume of 13.5L) during the treatment of synthetic coal wastewater at the mesophilic temperature of 27+/-5 degrees C. The hybrid reactors are a combination of UASB unit at the lower part and an anaerobic filter at the upper end. Synthetic wastewater with an average chemical oxygen demand (COD) of 2,240 mg/L, phenolics concentration of 752 mg/L and a mixture of volatile fatty acids was fed to three hybrid reactors. The fourth reactor, control system, was fed with a wastewater containing sodium acetate and mineral nutrients. Coal waste water contained phenol (490 mg/L); m-, o-, p-cresols (123.0, 58.6, 42 mg/L); 2,4-, 2,5-, 3,4- and 3,5-dimethyl phenols (6.3, 6.3, 4.4 and 21.3mg/L) as major phenolic compounds. A mixture of anaerobic digester sludge and partially granulated sludge (3:1) were used as seed materials for the start up of the reactors. Granules were observed after 45 days of operation of the systems. The granules ranged from 0.4 to 1.2 mm in diameter with good settling characteristics with an SVI of 12 mL/gSS. After granulation, the hybrid reactor performed steadily with phenolics and COD removal efficiencies of 93% and 88%, respectively at volumetric loading rate of 2.24 g COD/Ld and hydraulic retention time of 24 h. The removal efficiencies for phenol and m/p-cresols reached 92% and 93% (corresponding to 450.8 and 153 mg/L), while o-cresol was degraded to 88% (corresponding to 51.04 mg/L). Dimethyl phenols could be removed completely at all the organic loadings and did not contribute much to the residual organics. Biodegradation of o-cresol was obtained in the hybrid-UASB reactors.