Thorium fuel production and results from beginning of life irradiation

被引：21
作者：
Drera, Saleem S. [1 ]
Bjork, Klara Insulander [1 ,2 ]
Kelly, Julian F. [1 ,3 ,4 ]
机构：
[1] Thor Energy, NO-0255 Oslo, Norway
[2] Chalmers Univ Technol, Dept Appl Phys, Div Nucl Engn, SE-41296 Gothenburg, Sweden
[3] Matylda Sobieska Inst Energy Technol IFE, NO-1777 Halden, Norway
[4] Barbara Oberlander Inst Energy Technol IFE, NO-1777 Halden, Norway
来源：
PROGRESS IN NUCLEAR ENERGY | 2014年 / 72卷
关键词：
Thorium; Halden reactor; Test irradiation; Fuel production;
D O I：
10.1016/j.pnucene.2013.08.008
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：
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an introduction of thorium as the fertile component in mixed oxide fuel for conventional light water reactors. The utility of thorium as a component in today's light water reactors offers improved accident tolerance due to the superior material properties of thorium fuels over conventional uranium fuels. A few notable advantages include better thermal conductivity, higher melting point, higher oxide stability and superior spent fuel characteristics. Consequently, Thor Energy along with a consortium of industrial partners has established a fuel production and irradiation program aimed to license thorium fuels for use in today's light water reactors: Due to the morphology and physical properties of calcined thorium oxide powder, pellet fabrication used for standard uranium oxide fuels must be altered slightly for thorium bearing fuels to yield a product with acceptable theoretical densities, microstructure, and material integrity. At beginning of irradiation life fuel temperature data demonstrates improved fuel characteristics over standard uranium oxide fuel. Fuel centerline operating temperatures are 30-40 K less with a thorium mixed oxide fuel as compared to standard uranium fuel. (c) 2013 Elsevier Ltd. All rights reserved.
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页码：5 / 10
页数：6
相关论文
共 15 条
  • [1] Belle J., 1984, DOENE0060
  • [2] Study of Thorium-Plutonium Fuel for Possible Operating Cycle Extension in PWRs
    Bjork, Klara Insulander
    Lau, Cheuk Wah
    Nylen, Henrik
    Sandberg, Urban
    [J]. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2013, 2013
  • [3] Chen C.-F., 2013, THO2 CEO2 CE 1 UNPUB
  • [4] Chen C.-F., 2013, THO2 CEO2 CE 2 UNPUB
  • [5] Thermal diffusivity and conductivity of thorium-plutonium mixed oxides
    Cozzo, C.
    Staicu, D.
    Somers, J.
    Fernandez, A.
    Konings, R. J. M.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 416 (1-2) : 135 - 141
  • [6] The melting behaviour of plutonium dioxide: A laser-heating study
    De Bruycker, F.
    Boboridis, K.
    Poeml, P.
    Eloirdi, R.
    Konings, R. J. M.
    Manara, D.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2011, 416 (1-2) : 166 - 172
  • [7] Dekoussar V., 2005, 1450 TECDOC INT AT E
  • [8] Karam M, 2008, CW124950CONF002 AT E
  • [9] Katayama Y., 1963, HW76300 GEN EL CO
  • [10] Applicability of CeO2 as a surrogate for PuO2 in a MOX fuel development
    Kim, Han Soo
    Joung, Chang Yong
    Lee, Byung Ho
    Oh, Jae Yong
    Koo, Yang Hyun
    Heimgartner, Peter
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2008, 378 (01) : 98 - 104
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