Irradiation testing of enhanced uranium oxide fuels

被引：7

作者：

Bjork, Klara Insulander ^{[1
,8
]}

Kelly, Julian F. ^{[1
]}

Vitanza, Carlo ^{[1
]}

Drera, Saleem S. ^{[1
]}

Holcombe, Scott ^{[2
]}

Tverberg, Terje ^{[2
]}

Tuomisto, Harri ^{[3
]}

Wright, Jonathan ^{[4
]}

Sarsfield, Mark ^{[5
]}

Blench, Trevor ^{[7
]}

Yang, Jae Ho ^{[6
]}

Kim, Hyun-Gil ^{[6
]}

Kim, Dong-Joo ^{[6
]}

Lau, Cheuk W. ^{[1
]}

机构：

[1] Thor Energy, Karenslyst Alle 9c, NO-0278 Oslo, Norway

[2] Inst Energy Technol, Os Alle 5, NO-1777 Halden, Norway

[3] Fortum Corp, POB 1, FI-00048 Fortum, Finland

[4] Westinghouse Elect Sweden AB, SE-72163 Vasteras, Sweden

[5] Natl Nucl Lab, Chadwick House, Warrington WA3 6AE, Cheshire, England

[6] Korea Atom Energy Res Inst, 111 Daedeok Daero 989beon Gil, Daejeon, South Korea

[7] Steenkampskraal Thorium Ltd, 1st Floor,204 Soetdoring Bldg,7 Protea St, ZA-0157 Doringkloof, Centurion, South Africa

[8] Chalmers Univ Technol, Dept Phys, Div Subat & Plasma Phys, SE-41296 Gothenburg, Sweden

来源：

ANNALS OF NUCLEAR ENERGY | 2019年 / 125卷

关键词：

Uranium oxide fuel; Additives; Thorium; Cladding coating; Halden reactor; Test irradiation; THORIUM;

D O I：

10.1016/j.anucene.2018.10.050

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Enhanced uranium oxide fuel types are being tested in the Halden Research Reactor in Norway with the aim is to assess the effect that these enhancements have on fuel performance. Fuel temperatures, rod pressures and dimensional changes are being monitored online and an extensive post-irradiation examination programme is planned. Preliminary data show that fuel centerline temperatures can be lowered by addition of ThO2 to the fuel matrix, or by incorporating Cr or SiO2-TiO2 as a network structure within the fuel. In parallel, two types of cladding coatings are tested in order to investigate their in-core properties. No abnormal behaviour has been noted during the first 100 days of irradiation. (C) 2018 Elsevier Ltd. All rights reserved.

引用

页码：99 / 106

页数：8

共 10 条

[1]

Bennett P.J., 2008, F19HWR884 OECD HALD

[2] Thorium as an additive for improved neutronic properties in boiling water reactor fuel [J].

Bjork, Klara Insulander ;

Netterbrant, Christer .

ANNALS OF NUCLEAR ENERGY, 2018, 113 :470-475

[3] Commercial thorium fuel manufacture and irradiation: Testing (Th,Pu)O2 and (Th,U)O2 in the "Seven-Thirty" program [J].

Bjork, Klara Insulander ;

Drera, Saleem S. ;

Kelly, Julian F. ;

Vitanza, Carlo ;

Helsengreen, Christian ;

Tverberg, Terje ;

Sobieska, Matylda ;

Oberlander, Barbara C. ;

Tuomisto, Harri ;

Kekkonen, Laura ;

Wright, Jonathan ;

Bergmann, Uffe ;

Mathers, Daniel P. .

ANNALS OF NUCLEAR ENERGY, 2015, 75 :79-86

[4]

Kim D. -J., 2015, P KNS 2015 FALL M KY

[5] Fabrication of micro-cell UO2-Mo pellet with enhanced thermal conductivity [J].

Kim, Dong-Joo ;

Rhee, Young Woo ;

Kim, Jong Hun ;

Kim, Keon Sik ;

Oh, Jang Soo ;

Yang, Jae Ho ;

Koo, Yang-Hyun ;

Song, Kun-Woo .

JOURNAL OF NUCLEAR MATERIALS, 2015, 462 :289-295

[6] Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea [J].

Kim, Hyun-Gil ;

Yang, Jae-Ho ;

Kim, Weon-Ju ;

Koo, Yang-Hyun .

NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (01) :1-15

[7] Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating [J].

Kim, Hyun-Gil ;

Kim, Il-Hyun ;

Jung, Yang-Il ;

Park, Dong-Jun ;

Park, Jeong-Yong ;

Koo, Yang-Hyun .

JOURNAL OF NUCLEAR MATERIALS, 2015, 465 :531-539

[8] Reducing axial offset and improving stability in PWRs by using uranium-thorium fuel [J].

Lau, Cheuk Wah ;

Nylen, Henrik ;

Demaziere, Christophe ;

Sandberg, Urban .

PROGRESS IN NUCLEAR ENERGY, 2014, 76 :137-147

[9] Improvement of LWR thermal margins by introducing thorium [J].

Lau, Cheuk Wah ;

Demaziere, Christophe ;

Nylen, Henrik ;

Sandberg, Urban .

PROGRESS IN NUCLEAR ENERGY, 2012, 61 :48-56

[10] Thermal diffusivity and conductivity of thorium- uranium mixed oxides [J].

Saoudi, M. ;

Staicu, D. ;

Mouris, J. ;

Bergeron, A. ;

Hamilton, H. ;

Naji, M. ;

Freis, D. ;

Cologna, M. .

JOURNAL OF NUCLEAR MATERIALS, 2018, 500 :381-388

← 1 →