• 文献检索
  • 文档翻译
  • 深度研究
  • 学术资讯
  • Suppr Zotero 插件Zotero 插件
  • 邀请有礼
  • 套餐&价格
  • 历史记录
应用&插件
Suppr Zotero 插件Zotero 插件浏览器插件Mac 客户端Windows 客户端微信小程序
定价
高级版会员购买积分包购买API积分包
服务
文献检索文档翻译深度研究API 文档MCP 服务
关于我们
关于 Suppr公司介绍联系我们用户协议隐私条款
关注我们

Suppr 超能文献

核心技术专利:CN118964589B侵权必究
粤ICP备2023148730 号-1Suppr @ 2026

文献检索

告别复杂PubMed语法,用中文像聊天一样搜索,搜遍4000万医学文献。AI智能推荐,让科研检索更轻松。

立即免费搜索

文件翻译

保留排版,准确专业,支持PDF/Word/PPT等文件格式,支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述,25分钟生成高质量综述,智能提取关键信息,辅助科研写作。

立即免费体验

用于创新型无硼可溶小型模块化反应堆的真正优化的压水堆燃料格架

Truly-optimized PWR lattice for innovative soluble-boron-free small modular reactor.

作者信息

Nguyen Xuan Ha, Jang Seongdong, Kim Yonghee

机构信息

Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST), 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, Republic of Korea.

出版信息

Sci Rep. 2021 Jun 18;11(1):12891. doi: 10.1038/s41598-021-92350-5.

DOI:10.1038/s41598-021-92350-5
PMID:34145366
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC8213724/
Abstract

A novel re-optimization of fuel assembly and new innovative burnable absorber (BA) concepts are investigated in this paper to pursue a high-performance soluble-boron-free (SBF) small modular reactor (SMR), named autonomous transportable on-demand reactor module (ATOM). A truly optimized PWR (TOP) lattice concept has been introduced to maximize the neutron economy while enhancing the inherent safety of an SBF pressurized water reactor. For an SBF SMR design, the 3-D centrally-shielded BA (CSBA) design is utilized and another innovative 3-D BA called disk-type BA (DiBA) is proposed in this study. Both CSBA and DiBA designs are investigated in terms of material, spatial self-shielding effects, and thermo-mechanical properties. A low-leakage two-batch fuel management is optimized for both conventional and TOP-based SBF ATOM cores. A combination of CSBA and DiBA is introduced to achieve a very small reactivity swing (< 1000 pcm) as well as a long cycle length and high fuel burnup. For the SBF ATOM core, safety parameters are evaluated and the moderator temperature coefficient is shown to remain sufficiently and similarly negative throughout the whole cycle. It is demonstrated that the small excess reactivity can be well managed by mechanical shim rods with a marginal increase in the local power peaking, and a cold-zero shutdown is possible with a pseudo checker-board control rod pattern. In addition, a thermal-hydraulic-coupled neutronic analysis of the ATOM core is discussed.

摘要

本文研究了一种新型的燃料组件重新优化和新型创新可燃吸收体(BA)概念,以追求一种高性能的无硼(SBF)小型模块化反应堆(SMR),即自主按需运输反应堆模块(ATOM)。引入了一种真正优化的压水堆(TOP)栅格概念,以在提高SBF压水堆固有安全性的同时最大化中子经济性。对于SBF SMR设计,采用了三维中心屏蔽BA(CSBA)设计,并在本研究中提出了另一种创新的三维BA,即盘式BA(DiBA)。从材料、空间自屏蔽效应和热机械性能方面对CSBA和DiBA设计进行了研究。针对传统和基于TOP的SBF ATOM堆芯,优化了低泄漏两批燃料管理。引入CSBA和DiBA的组合,以实现非常小的反应性摆动(<1000pcm)以及长循环长度和高燃料燃耗。对于SBF ATOM堆芯,评估了安全参数,并且慢化剂温度系数在整个循环中显示出足够且相似的负值。结果表明,通过机械补偿棒可以很好地控制小的过剩反应性,局部功率峰值仅有少量增加,并且采用伪棋盘式控制棒模式可以实现冷零停堆。此外,还讨论了ATOM堆芯的热工水力耦合中子学分析。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/b77a7ee08ed3/41598_2021_92350_Fig13_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/d4e3165dcb3c/41598_2021_92350_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/e596cee27069/41598_2021_92350_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/f65dea45dfe5/41598_2021_92350_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/60f2d51d4c68/41598_2021_92350_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/2b2a166aa7f7/41598_2021_92350_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/59b6ec58625a/41598_2021_92350_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/da02a8911e06/41598_2021_92350_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/7280ee6ea755/41598_2021_92350_Fig8_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/e52347d4cf8f/41598_2021_92350_Fig9_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/3fedf16804bc/41598_2021_92350_Fig10_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/f120d1a641db/41598_2021_92350_Fig11_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/3f5528e70bb2/41598_2021_92350_Fig12_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/b77a7ee08ed3/41598_2021_92350_Fig13_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/d4e3165dcb3c/41598_2021_92350_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/e596cee27069/41598_2021_92350_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/f65dea45dfe5/41598_2021_92350_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/60f2d51d4c68/41598_2021_92350_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/2b2a166aa7f7/41598_2021_92350_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/59b6ec58625a/41598_2021_92350_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/da02a8911e06/41598_2021_92350_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/7280ee6ea755/41598_2021_92350_Fig8_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/e52347d4cf8f/41598_2021_92350_Fig9_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/3fedf16804bc/41598_2021_92350_Fig10_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/f120d1a641db/41598_2021_92350_Fig11_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/3f5528e70bb2/41598_2021_92350_Fig12_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/7e73/8213724/b77a7ee08ed3/41598_2021_92350_Fig13_HTML.jpg

相似文献

1
Truly-optimized PWR lattice for innovative soluble-boron-free small modular reactor.用于创新型无硼可溶小型模块化反应堆的真正优化的压水堆燃料格架
Sci Rep. 2021 Jun 18;11(1):12891. doi: 10.1038/s41598-021-92350-5.
2
Neutronic investigation of alternative & composite burnable poisons for the soluble-boron-free and long life civil marine small modular reactor cores.替代和复合可燃毒物的中子学研究,用于无可溶性硼和长寿命民用船用小型模块堆芯。
Sci Rep. 2019 Dec 20;9(1):19591. doi: 10.1038/s41598-019-55823-2.
3
Investigating the possibility of extending the BWR cycle length for 15 years of operation by mixing highly enriched UO fuel with burnable absorbers.研究通过混合高浓缩铀UO 燃料和可燃吸收剂将 BWR 运行周期延长 15 年的可能性。
Sci Rep. 2023 Jun 29;13(1):10518. doi: 10.1038/s41598-023-37615-x.
4
Investigation of the safety features of advanced PWR assembly using SiC, Zr, FeCrAl and SS-310 as cladding materials.使用碳化硅、锆、铁铬铝合金和310不锈钢作为包壳材料对先进压水堆组件安全特性的研究。
Sci Rep. 2021 Aug 31;11(1):17403. doi: 10.1038/s41598-021-96954-9.
5
Neutronic feasibility study of using a multipurpose MNSR for BNCT, NR, and NAA.使用多用途微型中子源反应堆进行硼中子俘获治疗、中子射线照相和中子活化分析的中子学可行性研究。
Appl Radiat Isot. 2020 Jul;161:109147. doi: 10.1016/j.apradiso.2020.109147. Epub 2020 Mar 26.
6
Neutronic and thermal-hydraulic analysis of new irradiation channels inside the Moroccan TRIGA Mark II research reactor core.摩洛哥TRIGA Mark II研究堆堆芯内新辐照通道的中子学和热工水力分析。
Appl Radiat Isot. 2016 Oct;116:178-84. doi: 10.1016/j.apradiso.2016.08.006. Epub 2016 Aug 12.
7
Neutronic performance characteristics of different LEU fuels in a proposed NIST research reactor.
Ann Nucl Energy. 2019 Jun;128. doi: 10.1016/j.anucene.2019.01.006.
8
The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code.使用 MCNPX 代码研究控制棒对 BWR 4 束堆芯反应性和通量分布的影响。
Sci Rep. 2021 Apr 22;11(1):8713. doi: 10.1038/s41598-021-88067-0.
9
Neutronic characteristic analysis of the GAMA microreactor.GAMA微型反应堆的中子学特性分析
Heliyon. 2024 May 3;10(9):e30707. doi: 10.1016/j.heliyon.2024.e30707. eCollection 2024 May 15.
10
Optimal controller design for reactor core power stabilization in a pressurized water reactor: Applications of gold rush algorithm.压水堆堆芯功率稳定的最优控制器设计:淘金算法的应用
PLoS One. 2024 Jan 26;19(1):e0296987. doi: 10.1371/journal.pone.0296987. eCollection 2024.