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Improved resource utilization by advanced burner reactors with breed-and-burn blankets

机译:先进的带有堆放毯的燃烧器反应堆提高了资源利用率

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摘要

Previous studies assessed the feasibility of designing Sodium-cooled Fast Reactors (SFR) in a novel Seed-and Blanket (S&B) configuration in which a significant fraction of the core power is generated by a radial metallic thorium-fueled blanket that operates in the Breed-and-Burn (B&B) mode. The radiation damage on the cladding material in both seed and blanket does not exceed the presently acceptable constraint of 200 Displacements per Atom (DPA). This paper investigates a number of blanket fuel options other than metallic thorium fuel, including thorium dioxide fuel, thorium hydride fuel, thorium nitride Fully Ceramic Encapsulated (FCM) fuel, and Pressurized Water Reactor (PWR) Used Nuclear Fuel (UNF) after limited reprocessing. Since the neutron spectrum of the oxide fueled blanket is softer than that of the reference metallic thorium fueled blanket, it can discharge its fuel at an average bumup of around 110 MWd/kg versus 65 MWd/kg of the metallic thorium. The two thorium hydride fueled blankets feature an even softer neutron spectrum than the oxide fueled blanket and, therefore, a higher average discharge burnup 192 MWd/kg and 245 MWd/kg when the H-to-Th ratio is, respectively, 0.5 and 2.0. The FCM fuel is composed of SiC matrix and cladding that is expected to self-anneal the neutrons induced damage. With the assumption that the FCM fuel will indeed be proven not limited by radiation damage, its discharge burnup could be up to 482 MWd/kg. As a result, the corresponding thorium utilization is the highest of all options examined close to 80 times the utilization of natural uranium in present Light Water Reactors (LWRs). The amount of Trans-Th isotopes accumulated in the thorium blanket per unit of generated electricity decreases as the blanket fuel is discharged at a higher burnup. Therefore, a higher discharge blanket bumup results in lower long-term radioactivity and radiotoxicity. It is also found that the U-232/U-233 ratio in the discharged thorium fuel is over 3 times higher in the thorium hydride than in the other blankets thus improving the thorium-hydride blanket's proliferation resistance. Softening of the blanket spectrum leads to softening of the seed spectrum region interfacing with the blanket and this enables to discharge the seed fuel at a higher average burnup. The higher discharge bumup of the seed fuel reduces the required reprocessing and fuel fabrication capacities per unit of generated electricity. The cores having softer neutron spectrum blankets also feature less positive feedback to sodium voiding and much more negative Doppler coefficient.
机译:先前的研究评估了设计新颖的种子和毯子(S&B)配置中的钠冷快堆(SFR)的可行性,在这种构型中,核心功率的很大一部分是由在品种中运行的径向金属or燃料毯产生的-烧录(B&B)模式。种子和毯子上的包层材料的辐射损伤均不超过目前可接受的每原子200位移(DPA)的限制。本文研究了有限的后处理方法,除了金属th燃料外,还研究了多种毯式燃料选择,包括二氧化or燃料,氢化or燃料,氮化or全陶瓷封装(FCM)燃料和压水堆(PWR)二手核燃料(UNF)。 。由于氧化物燃料覆盖层的中子光谱比参考金属metallic燃料覆盖层的中子光谱要软,因此它可以以约110 MWd / kg的平均沸腾排放燃料,而金属th为65 MWd / kg。两张氢化or为燃料的毯子的中子谱比氧化物为毯子的还要软,因此,当H / Th比分别为0.5和2.0时,平均放电燃耗更高,分别为192 MWd / kg和245 MWd / kg。 。 FCM燃料由SiC基体和覆层组成,可望对中子引起的损伤进行自退火。假设FCM燃料确实会受到辐射损害的限制,则其放电燃尽可能高达482 MWd / kg。结果,在所有检查的选项中,相应的th利用率是目前轻水反应堆(LWR)中天然铀利用率的80倍左右。随着毯式燃料以更高的燃耗放电,per气中每单位发电所积累的反式-Th同位素数量会减少。因此,较高的放电毯烧伤导致较低的长期放射性和放射毒性。还发现,排出的or燃料中的U-232 / U-233比率在氢化or中比在其他毯子中高3倍以上,从而提高了氢化or毯子的抗扩散性。毯状光谱的软化导致与毯状界面相接的种子光谱区域的软化,这使得能够以更高的平均燃耗排出种子燃料。种子燃料的较高排放量降低了单位发电量所需的后处理和燃料制造能力。具有较软的中子能谱层的核芯还具有较少的钠排泄正反馈和更多的负多普勒系数。

著录项

  • 来源
    《Progress in Nuclear Energy》 |2018年第7期|440-454|共15页
  • 作者单位

    Univ Calif Berkeley, Berkeley, CA 94720 USA;

    Univ Calif Berkeley, Berkeley, CA 94720 USA;

    Univ Calif Berkeley, Berkeley, CA 94720 USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:42:43

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