KR970003283A - Nuclear Fuel Pellets with Neutron Moderator - Google Patents

Nuclear Fuel Pellets with Neutron Moderator Download PDF

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Publication number
KR970003283A
KR970003283A KR1019950016765A KR19950016765A KR970003283A KR 970003283 A KR970003283 A KR 970003283A KR 1019950016765 A KR1019950016765 A KR 1019950016765A KR 19950016765 A KR19950016765 A KR 19950016765A KR 970003283 A KR970003283 A KR 970003283A
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KR
South Korea
Prior art keywords
nuclear fuel
moderator
neutron
pellet
central portion
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KR1019950016765A
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Korean (ko)
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KR0156379B1 (en
Inventor
이세엽
이찬영
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이세엽
이종훈
한국전력공사
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Priority to KR1019950016765A priority Critical patent/KR0156379B1/en
Priority to PCT/KR1996/000094 priority patent/WO1997001174A1/en
Publication of KR970003283A publication Critical patent/KR970003283A/en
Application granted granted Critical
Publication of KR0156379B1 publication Critical patent/KR0156379B1/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/901—Fuel

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

본 발명은 원자력 에너지를 이용하기 위하여 원자로에 투입하여 에너지를 발생시키는 핵연료에 관한 것으로 특히 핵연료의 사용효율을 극대화 한 중성자 감속재가 내장된 핵연료 펠릿에 관한 것으로 종래의 핵연료 펠릿은 성분이 균일하게 분포한 원통형으로 제작되어서 핵연료의 연소시에 중성자의 자기차폐(self-shielding)효과로 인하여 펠릿의 내부는 외부에 비하여 연소의 정도가 약하여 연료의 비효율적인 사용이 되므로 비경제적이며, 역으로 연료의 효율을 높이기 위하여 펠릿의 직경을 작게 하면 핵연료봉의 안정성이 낮아지며 또한 중성자 흡수물질이 원자로에 많아지고 원자로의 상부 쪽은 감지 및 냉각기능을 하는 물의 기포가 발생하여 중성자 감속기능이 급격히 낮아지는 문제점이 있었다.The present invention relates to a nuclear fuel that is injected into a reactor to generate energy in order to use nuclear energy, and more particularly relates to a nuclear fuel pellet with a neutron moderator, which maximizes the efficiency of use of the nuclear fuel. It is manufactured in a cylindrical shape, and due to the self-shielding effect of neutrons during the combustion of nuclear fuel, the inside of the pellet is less economical than the outside, which makes the fuel inefficient and inefficient. In order to increase the diameter of the pellet in order to increase the stability of the nuclear fuel rods, the neutron absorbing material is increased in the reactor, the upper side of the reactor has a problem that the neutron deceleration function is sharply lowered due to the bubbles of water to detect and cool.

본 발명에서는 핵연료의 연소시 중성자의 자기 차폐 효과를 최소화하여 핵연료의 연소를 균일하게 유도함과 동시에 핵연료봉의 안정성을 갖도록 하기 위하여 펠릿의 중심부분에 중성자의 에너지를 흡수하여 중성자가 쉽게 핵분열을 할 수 있는 상태로 유도하는 감속재를 장입하며 특히 감속재가 핵연료봉 내에서 전등 및 마찰에 의해 펠릿으로부터 이탈됨을 방지하도록한 이탈방지수단을 갖도록 함을 특징으로 함.In the present invention, in order to minimize the magnetic shielding effect of neutron shielding during the combustion of the fuel, to uniformly induce the combustion of the fuel and at the same time to ensure the stability of the fuel rod, the neutron can easily fission by absorbing the energy of the neutron in the center portion of the pellet Charge the moderator leading to the state, and characterized in that it has a release preventing means for preventing the moderator from being released from the pellet by the light and friction in the nuclear fuel rod.

Description

중성자 감속제가 내장된 핵연료 펠릿Nuclear Fuel Pellets with Neutron Reducer

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음Since this is an open matter, no full text was included.

제1도는 본 발명 펠릿의 일실시예를 보인 사시도, 제2도는 본 발명의 내부구성상태를 보인 사시도, 제3도의 (가)(나)(다)는 본 발명의 이탈방지수단을 보인 종단면도.1 is a perspective view showing an embodiment of the present invention pellets, Figure 2 is a perspective view showing an internal configuration of the present invention, Figure 3 (a) (b) (c) is a longitudinal cross-sectional view showing a departure preventing means of the present invention. .

Claims (8)

핵연료봉을 구성하는 구성단위로서 통상 원통형으로 핵연료의 재료분말을 압축 소결성형하여 형성하는 핵연료 펠릿에 있어서, 핵연료 펠릿(10)의 중심부분에 중성자의 에너지를 흡수하여 중성자가 쉽게 핵분열을 할 수 있는 상태로 유도하는 감속재(20)를 장입하여 이루어짐을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.In the nuclear fuel pellets formed by compression-sintering and molding the fuel powder in a cylindrical shape as a structural unit constituting the nuclear fuel rod, the neutron can easily fission by absorbing the neutron energy in the central portion of the nuclear fuel pellet 10. Nuclear fuel pellets with a built-in neutron moderator, characterized in that made by charging the moderator 20 to guide the state. 제1항에 있어서, 핵연료 펠릿(10)의 중심부분에 장입되는 감속재(20)는 흑연임을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.The fuel pellet with nuclear neutron moderator according to claim 1, wherein the moderator (20) charged in the central portion of the fuel pellet (10) is graphite. 제1항 또는 제2항에 있어서, 핵연료 펠릿(10)의 중심부분에 장입되는 감속재(20)는 핵연료봉 내에서 진동및 마찰에 의해 펠릿(10)으로부터 이탈이 방지되도록 이탈방지수단을 구비함을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.The method of claim 1 or claim 2, wherein the moderator 20 is charged to the central portion of the nuclear fuel pellet 10 is provided with a departure prevention means to prevent the departure from the pellet 10 by vibration and friction in the nuclear fuel rod. Nuclear fuel pellets containing a neutron moderator. 제3항에 있어서, 핵연료 펠릿(10)의 중심부분에 장입되는 감속재(20)가 이탈되지 않도록 하는 이탈방지수단은 펠릿(10)의 내부의 하측부에 걸림턱(11)을 형성하여 구성함을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.According to claim 3, wherein the separation preventing means for preventing the deceleration material 20 is inserted into the central portion of the nuclear fuel pellet 10 is formed by forming a locking jaw (11) in the lower side of the inside of the pellet (10) Nuclear fuel pellets containing a neutron moderator. 제3항에 있어서, 핵연료 펠릿(10)의 중심부분에 장입되는 감속재(20)가 이탈되지 않도록 하는 이탈방지수단은 감속재(20)의 하측 반경이 상측 반경보다 좁게 형성함을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.The neutron moderator according to claim 3, wherein the release preventing means for preventing the moderator 20 inserted into the central portion of the nuclear fuel pellet 10 from being separated is formed such that the lower radius of the moderator 20 is narrower than the upper radius. Nuclear fuel pellets. 제3항에 있어서, 핵연료 펠릿(10)의 중심부분에 장입되는 감속재(20)가 이탈 방지되도록 하는 이탈방지수단은 내측의 감속재(20)의 단면형상을 방사형으로 형성함을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.4. The neutron moderator according to claim 3, wherein the release preventing means for preventing the release of the moderator 20 inserted into the central portion of the nuclear fuel pellet 10 is radially formed in the cross-sectional shape of the moderator 20 inside. Nuclear fuel pellets. 제3항에 있어서, 핵연료 펠릿(10)의 중심부분에 장입되는 감속재(20)가 이탈 방지되도록 하는 이탈방지수단은 내측의 감속재(20)의 단면형상을 "C" 형으로 형성함을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.The method of claim 3, wherein the separation preventing means for preventing the departure of the moderator 20 inserted into the central portion of the nuclear fuel pellet 10 is characterized in that the cross-sectional shape of the moderator 20 of the inner side to form a "C" shape. Nuclear fuel pellets with built-in neutron moderators. 제3항에 있어서, 핵연료 펠릿(10)의 중심부분에 장입되는 감속재(20)가 이탈 방지되도록 하는 이탈방지수단은 내측의 감속재(20)의 단면형상을 나선형으로 형성함을 특징으로 하는 중성자 감속재가 내장된 핵연료 펠릿.4. The neutron moderator according to claim 3, wherein the release preventing means for preventing the release of the moderator 20 inserted into the central portion of the nuclear fuel pellet 10 forms a cross-sectional shape of the moderator 20 inside. Nuclear fuel pellets. ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.※ Note: The disclosure is based on the initial application.
KR1019950016765A 1995-06-21 1995-06-21 Nuclear pellet with neutron moderator KR0156379B1 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
KR1019950016765A KR0156379B1 (en) 1995-06-21 1995-06-21 Nuclear pellet with neutron moderator
PCT/KR1996/000094 WO1997001174A1 (en) 1995-06-21 1996-06-21 Nuclear fuel pellet

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Application Number Priority Date Filing Date Title
KR1019950016765A KR0156379B1 (en) 1995-06-21 1995-06-21 Nuclear pellet with neutron moderator

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KR970003283A true KR970003283A (en) 1997-01-28
KR0156379B1 KR0156379B1 (en) 1998-12-15

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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8557148B2 (en) 2009-11-23 2013-10-15 Korea Atomic Energy Research Institute Method for fabricating sintered annular nuclear fuel pellet through rod-inserted sintering
US8585939B2 (en) 2009-09-03 2013-11-19 Korea Atomic Energy Research Institute Method for preparing sintered annular nuclear fuel pellet

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11367537B2 (en) * 2017-05-09 2022-06-21 Westinghouse Electric Company Llc Annular nuclear fuel pellets with central burnable absorber

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4124659A (en) * 1973-05-02 1978-11-07 S.A.E.S. Getters S.P.A. Gettering in nuclear fuel elements
US4668468A (en) * 1984-06-01 1987-05-26 Electric Power Research Institute, Inc. Reactivity control of nuclear fuel pellets by volumetric redistribution of fissile, fertile and burnable poison material
US4687629A (en) * 1986-01-27 1987-08-18 Westinghouse Electric Corp. Fuel rod with annular nuclear fuel pellets having same U-235 enrichment and different annulus sizes for graduated enrichment loading
US4783311A (en) * 1986-10-17 1988-11-08 Westinghouse Electric Corp. Pellet-clad interaction resistant nuclear fuel element

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8585939B2 (en) 2009-09-03 2013-11-19 Korea Atomic Energy Research Institute Method for preparing sintered annular nuclear fuel pellet
US8557148B2 (en) 2009-11-23 2013-10-15 Korea Atomic Energy Research Institute Method for fabricating sintered annular nuclear fuel pellet through rod-inserted sintering

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Publication number Publication date
KR0156379B1 (en) 1998-12-15
WO1997001174A1 (en) 1997-01-09

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