Advanced Doped UO2 Pellets in LWR Applications

颗粒 材料科学 弹丸 核工程 核燃料 乏核燃料 烧结 复合材料 工程类
作者
Jakob ARBORELIUS,Karin BACKMAN,L. Hallstadius,Magnus Limbäck,Jimmy NILSSON,B. Rebensdorff,Gang Zhou,Koji Kitano,Reidar LÖFSTRÖM,Gunnar RÖNNBERG
出处
期刊:Journal of Nuclear Science and Technology [Taylor & Francis]
卷期号:43 (9): 967-976 被引量:18
标识
DOI:10.3327/jnst.43.967
摘要

The nuclear industry strives to reduce the fuel cycle cost, enhance flexibility and improve the reliability of operation. This can be done by both increasing the fuel weight and optimizing rod internal properties that affect operational margins. Further, there is focus on reducing the consequences of fuel failures. To meet these demands Westinghouse has developed ADOPT (Advanced Doped Pellet Technology) UO2 fuel containing additions of chromium and aluminium oxides. This paper presents results from the extensive investigation program which covered examinations of doped and reference standard pellets both in the manufactured and irradiated states. The additives facilitate pellet densification during sintering and enlarge the pellet grain size. The final manufactured doped pellets reach about 0.5% higher density within a shorter sintering time and a five fold larger grain size compared with standard UO2 fuel pellets. The physical properties of the pellets, including heat capacity, thermal expansion coefficient, melting temperature, thermal diffusivity, have been investigated and differences between the doped and standard UO2 pellets are small. The in-reactor performance of the ADOPT pellets has been investigated in pool-side and hotcell Post Irradiation Examinations (PIEs), as well as in the Studsvik R2 test reactor. The investigations have identified three areas of improved operational behaviour: Reduced fission gas release, improved PCI performance thanks to increased pellet plasticity and higher resistance against post-failure degradation. Fuel segments have been exposed to ramp tests and enhanced power steady-state operation in the Studsvik R2 reactor after base-irradiation to above 30 MWd/kgU in a commercial BWR. ADOPT reveals up to 50% lower fission gas release than standard UO2 pellets. The fuel degradation behaviour has been studied in two oxidizing tests, a thermal-microbalance test and an erosion test under irradiation. The tests show that ADOPT pellets have a reduced rate of fuel washout, as compared to standard UO2 pellets. Fuel rods with ADOPT pellets have been irradiated in several light water reactors (LWRs) since 1999, including two full SVEA-96 Optima2 reloads in 2005.
最长约 10秒,即可获得该文献文件

科研通智能强力驱动
Strongly Powered by AbleSci AI
科研通是完全免费的文献互助平台,具备全网最快的应助速度,最高的求助完成率。 对每一个文献求助,科研通都将尽心尽力,给求助人一个满意的交代。
实时播报
深情海秋发布了新的文献求助10
刚刚
if应助盒子采纳,获得20
1秒前
李青溟完成签到,获得积分10
1秒前
科研通AI6.2应助zz采纳,获得10
1秒前
缓慢访冬完成签到,获得积分20
1秒前
levi发布了新的文献求助10
1秒前
kikyou关注了科研通微信公众号
2秒前
桐桐应助骑猪兜风采纳,获得10
2秒前
着急的彩虹完成签到,获得积分20
3秒前
科研通AI6.4应助lr采纳,获得10
3秒前
fjh发布了新的文献求助10
3秒前
4秒前
梨有理想发布了新的文献求助10
4秒前
地蛋完成签到,获得积分10
4秒前
v0id应助李青溟采纳,获得10
4秒前
喜悦初彤完成签到,获得积分10
4秒前
5秒前
YOLO完成签到,获得积分20
6秒前
6秒前
星辰大海应助syd采纳,获得10
6秒前
大个应助科研通管家采纳,获得10
6秒前
6秒前
6秒前
小二郎应助科研通管家采纳,获得10
6秒前
6秒前
大模型应助科研通管家采纳,获得10
6秒前
6秒前
6秒前
小蘑菇应助科研通管家采纳,获得10
6秒前
隐形曼青应助科研通管家采纳,获得10
7秒前
7秒前
7秒前
7秒前
8秒前
8秒前
9秒前
alna完成签到,获得积分10
9秒前
华仔应助骁龙采纳,获得30
11秒前
11秒前
源柒YuanQi发布了新的文献求助10
11秒前
高分求助中
(应助此贴封号)【重要!!请各用户(尤其是新用户)详细阅读】【科研通的精品贴汇总】 10000
The anomeric effect 1000
Principles of town planning: translating concepts to applications 1000
1 Peter and Christ's Descent to the Dead in Its Early Christian Reception 700
Nature-Inspired Computing: Concepts, Methodologies, Tools, and Applications 600
Perfectionism in School 600
Organizational Behavior 510
热门求助领域 (近24小时)
化学 材料科学 医学 生物 纳米技术 工程类 有机化学 化学工程 生物化学 计算机科学 内科学 物理 复合材料 催化作用 细胞生物学 无机化学 光电子学 物理化学 电极 基因
热门帖子
关注 科研通微信公众号,转发送积分 7730707
求助须知:如何正确求助?哪些是违规求助? 9282214
关于积分的说明 20149598
捐赠科研通 7308170
什么是DOI,文献DOI怎么找? 3303486
关于科研通互助平台的介绍 2456377
邀请新用户注册赠送积分活动 2312083