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1. WO2006092970 - FUEL BUNDLE FOR PRESSURIZED-WATER REACTOR AND METHOD OF DESIGNING FUEL BUNDLE

Publication Number WO/2006/092970
Publication Date 08.09.2006
International Application No. PCT/JP2006/302876
International Filing Date 17.02.2006
IPC
G21C 3/28 2006.01
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements or their assemblies; Selection of substances for use as reactor fuel elements
02Fuel elements
28with fissile or breeder material in solid form within a non-active casing
G21C 3/328 2006.01
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements or their assemblies; Selection of substances for use as reactor fuel elements
30Assemblies of a number of fuel elements in the form of a rigid unit
32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
326comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
328Relative disposition of the elements in the bundle lattice
CPC
G21C 3/28
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
02Fuel elements
28with fissile or breeder material in solid form within a non-active casing
G21C 3/328
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
30Assemblies of a number of fuel elements in the form of a rigid unit
32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
326comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
328Relative disposition of the elements in the bundle lattice
Y02E 30/30
YSECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
30Energy generation of nuclear origin
30Nuclear fission reactors
Applicants
  • 三菱重工業株式会社 MITSUBISHI HEAVY INDUSTRIES, LTD. [JP]/[JP] (AllExceptUS)
  • 濱崎 学 HAMASAKI, Manabu (UsOnly)
  • 星 雅也 HOSHI, Masaya (UsOnly)
  • 田淵 士郎 TABUCHI, Shiro (UsOnly)
Inventors
  • 濱崎 学 HAMASAKI, Manabu
  • 星 雅也 HOSHI, Masaya
  • 田淵 士郎 TABUCHI, Shiro
Agents
  • 酒井 宏明 SAKAI, Hiroaki
Priority Data
2005-05275928.02.2005JP
Publication Language Japanese (JA)
Filing Language Japanese (JA)
Designated States
Title
(EN) FUEL BUNDLE FOR PRESSURIZED-WATER REACTOR AND METHOD OF DESIGNING FUEL BUNDLE
(FR) GRAPPE DE COMBUSTIBLE POUR REACTEUR A EAU SOUS PRESSION ET PROCEDE DE CONCEPTION DE GRAPPE DE COMBUSTIBLE
(JA) 加圧水型原子炉の燃料集合体及び燃料集合体の設計方法
Abstract
(EN)
There are provided a fuel bundle for pressurized-water reactor and a method of designing a fuel bundle. In the forming of a fuel bundle through charging of fuel pellets obtained by burning/hardening of uranium oxide in a fuel cladding tube of zirconium alloy to thereby obtain fuel rods and bundling of multiple fuel rods in a lattice form, there is determined region A where the weight of uranium loaded in the fuel bundle is increased by an increase of the outside diameter of fuel pellets and where any increment of reactivity attributed to drop of combustion degree accompanying the same exceeds any drop of reactivity caused by insufficient moderation resulting from a decrease of moderating material due to the increase of the outside diameter of fuel pellets, and the diameter of fuel pellets is established within the reactivity increase region A.
(FR)
La présente invention concerne une grappe de combustible pour réacteur à eau sous pression et un procédé de conception d’une grappe de combustible. Dans la formation d’une grappe de combustible en chargeant des pastilles de combustible obtenues en brûlant/durcissant de l’oxyde d’uranium dans un tube de gaine de combustible d’alliage de zirconium pour ainsi obtenir des barres de combustible et en groupant de multiples barres de combustible pour obtenir une forme de treillis, il existe une région déterminée A où le poids de l’uranium chargé dans la grappe de combustible augmente en augmentant le diamètre extérieur des pastilles de combustible et où un incrément quelconque de réactivité attribué pour réduire le degré de combustion l’accompagnant dépasse une réduction quelconque de réactivité entraînée par une modération insuffisante résultant d’une réduction de matériau de modération en raison de l’augmentation du diamètre extérieur des pastilles de combustible, et le diamètre de pastilles de combustible est établi à l’intérieur de la région d’augmentation de réactivité A.
(JA)
 加圧水型原子炉の燃料集合体及び燃料集合体の設計方法においてウラン酸化物を焼き固めた燃料ペレットをジルコニウム合金製の燃料被覆管に充填して燃料棒を形成し、燃料棒を複数格子状に束ねて燃料集合体を構成し、燃料ペレットの外径が増加することで燃料集合体に装荷されたウラン重量が増加し、それに伴う燃焼度の低下による反応度の増加分が、燃料ペレットの外径の増加による減速材の減少がもたらす減速不足によって生じる反応度の低下分を上回る領域Aを求め、この反応度が上回る領域A内で燃料ペレットの直径を設定する。
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