日本利用钚的方法

【日本《原子能视野》 1998年 7月号第4 8— 5 0页报道】　日本从开发核能初期开始 ,便从有效利用铀资源的观点出发 ,把处理核电站的乏燃料、回收钚以及再循环利用铀作为基本的原子能政策。从国外的利用实绩来看 ,钚用于轻水堆(用于热堆 )可以说是目前钚的最切实可行的利用方法。这将是今后数十年钚利用的最主要途径。另一方面 ,到 1996年年底为止 ,日本在国外已后处理的可裂变钚大约 10 .5吨 ,这些钚仍留在国外。以不拥有剩余钚原则为基础 ,今后切实按照此原则 ,把钚作为反应堆燃料加以利用是很重要的。因此 ,日本计划从 1999年开始 ,有 2…     

多重钚循环

【英国《国际核工程》2003年2月刊报道】 核能机构实施了一项旨在确定在压水堆(PWR)中钚的有效循环次数的标准评估作业,结果刊登在《钚循环物理》上。 目前,以MOX燃料的形式进行钚循环利用已在商业规模上得到采用。MOX燃料的卸料燃耗基本上与UO2燃料相同。因此,目前PWR使用的MOX燃料将在燃耗达到40～45 MWd/kg时卸出。达到这一燃耗所需的初始钚含量随着钚源的不同而变化。MOX在PWR中的使用经验是可以肯定的,没有突出的操作或安全问题需要解决。 然而,情况并非一成不变。最基本的变化是卸料燃耗在不断上升,以及对卸出的MOX燃料…     

运往加拿大的钚如烫手的山芋

【《基督教科学缄言报》1999年11月30日报道】 Parallex项目——对来自俄罗斯和美国核弹头中的钚进行最终处置的试验——就象是一把利剑,插向了加拿大具有缔造和平传统的外交政策的犁头。 1999年12月2日,经批准,第一批少量武器级钚的样品已经离开密歇根州,被运往加拿大安大略省的乔克里弗研究堆,准备进行为期3年的“试验性燃烧”。在大约10年内,该试验可能会为加拿大打开商业核电站使用过剩的军用钚做燃料的大门。 但是,反对者对此提出了批评,这种尝试将会有把加拿大带入危险的钚贸易和使加拿大成为全球核废物倾倒地的风险。他们甚至对这…     

朝鲜项目的延误使韩国钚利用战略复杂化

【国际原子能机构《报刊文摘》 1998年第 15 9期报道】　韩国官员称 ,普遍认为在朝鲜推迟建设两座压水堆 ,很可能会影响韩国电力公司 (Kepco)在其最老的一个反应堆的场地已闲置贮存空间的情况下 ,执行其海外乏燃料后处理以及分离钚在动力堆中再利用。官方称 ,Kepco和韩国对于是否走日本的路子、开始一个商业规模的钚利用战略犹豫不决。尽管如此 ,Kepco领导层于 1997年告知韩国科技部 (MOST) ,Kepco仍然希望后处理国外的乏燃料。在第三方的参与下 ,并根据双方核合作协议 ,要求美韩双方就韩国在法国或英国后处理由美国提供的燃料必须征得…     

燃钚反应堆

【法国《研究》1999年第325期和法国《科学与生活》2000年第988期报道】 80年代放弃的高温核反应堆再次研究用于销毁俄罗斯军用钚以及用于发电和供热。为了销毁裁军协议中规定的50吨钚,美国议会计划在2000年向GT-MHR反应堆(燃汽轮机模块氦反应堆)提供1000万美元。由美国通用原子能公司于1993年倡议的该计划,1996年得到法国FRAMATOME的支持,1997年又得到日本FUJI电力公司的支持。2009年将在俄罗斯的托木斯克建造一座原型堆。这种类型的反应堆只能燃烧钚。 对于该项目,俄罗斯的专家保证,在相等的电功率上,该反应堆的有效性将比其目前…     

钚

在多数核电厂产生的能量中,有三分之一以上来自钚。在此,钚是作为副产品产生的。 钚曾经是天然存在的,但除痕量外,在地壳中现在已找不到这种元素。 在我们的生物圈里,有几吨钚,这些钚是20世纪50～60年代大气层武器试验的遗留物。 钚,尤其在吸入体内后会产生放射危害。因此操作时,必须采取适当的防护措施。 将反应堆以及拆卸核武器产生的钚加入核燃料循环,便成为一种宝贵的能源。 钚的同位素主要有: 钚-238(半衰期88年) 钚-239,易裂变(半衰期24000年) 钚-240,易裂变(半衰期6500年) 钚-241,易裂变(半衰期14年) 钚-242(半衰期37600年)…     

钚与后处理铀在轻水堆中的重新循环

【英国《国际核工程》1989年专刊第71页报道】法国核工业正注重使钚和后处理铀两种燃料重新循环。钚可用作铀-235的替代裂变燃料而制成铀-钚混合氧化物燃料(MOX);而后处理铀必须被转换和再被     

Multilateral Assessment of the Fast Reactor System as a Component of the Future Sustainable Nuclear Energy and Paths for the System Deployment

The paper reviews main findings of the Joint Assessment Study on a Nuclear Energy System (NES) based on a Closed Nuclear Fuel Cycle with Fast Reactors (CNFC-FRs) that was performed within the IAEA project INPRO.     

核能在新时期国家能源可持续发展战略中的地位和作用(英文)

从国家能源安全与能源可持续发展的角度论述了核能的优势地位和作用,及核能在满足能源和电力安全供应需求、缓解生态环境污染和降低温室气体排放等方面的作用。讲述了中国能源安全和可持续发展面临的挑战和严峻形势,指出发展核能是中国优化能源结构的客观要求,是我国未来能源及电力安全供应的重要保证。阐明了发展核能是实现中国能源与电力可持续发展的必然选择,核能利用符合循环经济的原则。研究分析了核电发展对中国未来生态环境保护的贡献,并对中国核能发展提出了一些建议。     

钚年龄评估技术

在军控核查技术中应用钚的年龄属性对核弹头认证和“禁产公约”监督具有非常重要的意义。根据^241Pu的不同衰变模式，对母核和子核衰变伴随的γ辐射随时间的变化、各种情况下子核与母核的原子比随时间的变化规律等进行了描述。研究表明，通过某种手段获得^241Pu和^241Am的原子比或测量γ辐射可确定钚的年龄。     

Temperature Effect on Plutonium Leach Rate of Nuclear Waste Glass

The two kinds of nuclear waste glass with similar composition, a ²³⁸Pu-doped and nonradioactive waste glass, were leached under the ISO-test conditions at temperature between 23 and 90°C. An activation energy of 22±10kJ/mole was obtained from the initial leach rates of Pu, which was much lower than the 78±9kJ/mole obtained from those of Si, Na, Sr and Cs, It is suggested that in the initial stages of leaching. Pu is not released from the waste glass with the same mechanisms as the releases of Si, Na, Sr and Cs, but the dissolution of hydrous plutonium dioxide PuO₂·_xH₂O formed on the glass surface becomes predominant. In the long duration tests (<32d), the release of Pu appears to be affected by the solubility of PuO₂·_xH₂O remaining in the leached surface layers.     

Utilization Factor of Nuclear Material in LMFBR

The effects of γ-irradiation on a simulated nuclear waste glass were studied by electron spin resonance spectroscopy (ESR), and were compared with the results on silica glass and Pyrex glass. Three kinds of glasses were γ-irradiated up to the dose of 1.22 MGy and the ESR spectra were obtained. The intensity of ESR spectra were obtained as a function of irradiation dose and annealing temperature.

The spectrum of the waste glass was characteristic of two typical peaks, Peak 1 was the strong resonance at g=4.3 showing the existence of four coordinated Fe³⁺ and Peak 2 was the weak and broad resonance at g= 2.0 showing the existence of six coordinated Fe³⁺. The ESR spectra of the waste glass before and after γ-irradiation were almost overlapped and a little difference only in the intensity was observed. While in silaca glass and Pyrex glass, the peaks from E'γ center and boron-oxygen hole center (BOHC) were observed to arise after irradiation. The absolute intensity of. Peaks 1 and 2 described above changed in complicated way depending on the dose. The result suggests oxidation or reduction of iron takes place in the waste glass depending on the dose. The isochronal annealing of irradiated glasses shows most of γ-ray- induced damages in the waste glass are restored even at room temperature, although most of the damages in silica glass and Pyrex glass are disappeared at the temperature from 550 to 600 K. The results show that the waste glass with a few weight percent of iron is resistent to radiation than other commercial glasses.     

美国先进核燃料循环计划概述及对我国的启发

美国已重启核能计划,其中先进的核燃料循环计划是核能计划的核心。若这一计划得以顺利实施,将可以消除人们曾担忧的核能开发中的三大问题,核扩散、高放废物的处置和铀资源的可持续性问题。美国这一计划对我国的核能发展应有一些启发。     

Effective Utilization of Weapon-Grade Plutonium to Upgrade Repeatedly-Reprocessed Mixed-Oxide Fuel for Use in Pressurized Water Reactors

A “Multiple Recycling” mode of fuel management is proposed for effectively utilizing weapon-grade plutonium from discarded military material to compensate plutonium degradation in repeatedly-reprocessed mixed-oxide (MOX) fuel. Comparative calculations on core performance are undertaken for comparison between the proposed fuel management mode of Multiple Recycling—using recovered depleted plutonium upgraded by admixture with weapon-grade plutonium while retaining unincreased the total plutonium” content—and a reference mode of using repeatedly reprocessed spent MOX fuel with plutonium upgraded through increase of the plutonium content. Multiple Recycling proves all calculated safety parameters to be retained unimpaired through multiple cycles of MOX fuel reprocessing, whereas in the reference mode of refueling with spent MOX fuel reprocessed without upgrading with weapon-grade plutonium, many of the calculated safety parameters come to exceed stipulated limits with repetition of fuel cycles. Moreover, Multiple Recycling mode can be implemented with application solely of techniques already practiced in the fabrication of MOX fuel.     

由世纪之交核能发展中的三件大事看核能发展的前景

简述了世纪之交核能发展中的三件大事 :第 4代核电的技术政策研究 ;俄罗斯总统发出推动核电发展的倡议 ;美国颁布新的国家能源政策。还展望了世界核能发展的前景 ,并对我国核电发展提出建议     

Specific fuel rod thermomechanical studies for the Advanced Plutonium fuel assembly concept

In order to burn plutonium in PWRs, an innovative assembly has been proposed: the Advanced Plutonium fuel Assembly (APA) concept. This heterogeneous assembly is based on the standard 17x17 geometry, replacing 144 classical UO₂ fuel rods by 36 large fuel rods containing plutonium in an inert matrix. To accommodate the high power and burn-up, a thin annular geometry has been proposed. However, the design of such assembly is a challenge due to the highly innovative fuel rod concept. Regarding the fabrication, different processes are under investigation: concentric claddings with annular ceramic pellets (cercer), ceramic/metal fuel (cermet) metallurgically bonded to the claddings, vibrocompacted fuel. This paper focuses on thermomechanical studies performed for the two first concepts, in view of a future selection between the different processes. The analysis concerns temperature profiles, fuel-cladding gap evolutions and cladding buckling risk. Regarding those parameters, the conclusion is that the cermet matrix presents satisfactory conditions: operating at very low temperatures and no buckling risk.     

钍基重水核能系统燃料的物理特性研究

对全铀CANFLEX燃料和含钍CANFLEX燃料的物理特性进行了研究。用WIMS-AECL程序计算了参考栅元的冷却剂空泡反应性、燃耗等参数。通过与铀燃料的对比,展示了含钍燃料在安全性和经济性上的特点还特别介绍WIMS-AECL程序在使用过程中的参数选择方法,