CA2099324A1 - Faisceau de combustible pour surgenerateur ralenti a l'eau lourde - Google Patents

Faisceau de combustible pour surgenerateur ralenti a l'eau lourde

Info

Publication number: CA2099324A1
Authority: CA; Canada
Prior art keywords: fuel; region; bundle; fissile material; fissile
Prior art date: 1993-06-28
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.): Abandoned

Application number

CA002099324A

Other languages

English (en)

Inventor

Adi R. Dastur

Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)

Atomic Energy of Canada Ltd AECL

Original Assignee

Atomic Energy of Canada Ltd AECL

Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)

1993-06-28

Filing date

1993-06-28

Publication date

1994-02-19

1993-06-28 Application filed by Atomic Energy of Canada Ltd AECL filed Critical Atomic Energy of Canada Ltd AECL

1993-06-28 Priority to CA002099324A priority Critical patent/CA2099324A1/fr

1994-02-19 Publication of CA2099324A1 publication Critical patent/CA2099324A1/fr

Status Abandoned legal-status Critical Current

Links

239000000446 fuel Substances 0.000 title claims abstract description 118
XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 title claims abstract description 28
239000000463 material Substances 0.000 claims abstract description 65
238000000034 method Methods 0.000 claims abstract description 21
238000001228 spectrum Methods 0.000 claims abstract description 13
238000009395 breeding Methods 0.000 claims abstract description 3
230000001488 breeding effect Effects 0.000 claims abstract description 3
JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims description 18
OYEHPCDNVJXUIW-FTXFMUIASA-N 239Pu Chemical compound [239Pu] OYEHPCDNVJXUIW-FTXFMUIASA-N 0.000 claims description 3
ZSLUVFAKFWKJRC-UHFFFAOYSA-N thorium Chemical compound [Th] ZSLUVFAKFWKJRC-UHFFFAOYSA-N 0.000 claims 2
JFALSRSLKYAFGM-OIOBTWANSA-N uranium-235 Chemical compound [235U] JFALSRSLKYAFGM-OIOBTWANSA-N 0.000 claims 2
229910052778 Plutonium Inorganic materials 0.000 description 15
OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 15
229910052770 Uranium Inorganic materials 0.000 description 13
230000008569 process Effects 0.000 description 10
230000004992 fission Effects 0.000 description 9
238000004519 manufacturing process Methods 0.000 description 9
239000002826 coolant Substances 0.000 description 8
239000000126 substance Substances 0.000 description 6
238000012958 reprocessing Methods 0.000 description 4
239000002915 spent fuel radioactive waste Substances 0.000 description 4
230000004048 modification Effects 0.000 description 3
238000012986 modification Methods 0.000 description 3
OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 3
FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 3
DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
238000010521 absorption reaction Methods 0.000 description 2
238000006243 chemical reaction Methods 0.000 description 2
238000005516 engineering process Methods 0.000 description 2
230000004907 flux Effects 0.000 description 2
230000014509 gene expression Effects 0.000 description 2
239000007788 liquid Substances 0.000 description 2
239000003758 nuclear fuel Substances 0.000 description 2
239000008188 pellet Substances 0.000 description 2
230000009257 reactivity Effects 0.000 description 2
238000000926 separation method Methods 0.000 description 2
229910052708 sodium Inorganic materials 0.000 description 2
239000011734 sodium Substances 0.000 description 2
239000002699 waste material Substances 0.000 description 2
XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
229910001093 Zr alloy Inorganic materials 0.000 description 1
238000009825 accumulation Methods 0.000 description 1
230000008901 benefit Effects 0.000 description 1
230000005540 biological transmission Effects 0.000 description 1
239000000919 ceramic Substances 0.000 description 1
238000012993 chemical processing Methods 0.000 description 1
230000006378 damage Effects 0.000 description 1
230000007423 decrease Effects 0.000 description 1
238000006073 displacement reaction Methods 0.000 description 1
238000000605 extraction Methods 0.000 description 1
231100001261 hazardous Toxicity 0.000 description 1
239000007924 injection Substances 0.000 description 1
238000002347 injection Methods 0.000 description 1
150000002500 ions Chemical class 0.000 description 1
230000007774 longterm Effects 0.000 description 1
239000000203 mixture Substances 0.000 description 1
238000012545 processing Methods 0.000 description 1
239000000243 solution Substances 0.000 description 1
125000006850 spacer group Chemical group 0.000 description 1
230000003595 spectral effect Effects 0.000 description 1
230000001629 suppression Effects 0.000 description 1

Classifications

- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/26—Control of nuclear reaction by displacement of the moderator or parts thereof by changing the moderator concentration
- G21C7/27—Spectral shift control
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising 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
- G21C3/328—Relative disposition of the elements in the bundle lattice
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
- 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

Landscapes

Physics & Mathematics (AREA)
Engineering & Computer Science (AREA)
Plasma & Fusion (AREA)
General Engineering & Computer Science (AREA)
High Energy & Nuclear Physics (AREA)
Spectroscopy & Molecular Physics (AREA)
Chemical & Material Sciences (AREA)
Chemical Kinetics & Catalysis (AREA)
Monitoring And Testing Of Nuclear Reactors (AREA)

CA002099324A 1993-06-28 1993-06-28 Faisceau de combustible pour surgenerateur ralenti a l'eau lourde Abandoned CA2099324A1 (fr)

Priority Applications (1)

Application Number	Priority Date	Filing Date	Title
CA002099324A CA2099324A1 (fr)	1993-06-28	1993-06-28	Faisceau de combustible pour surgenerateur ralenti a l'eau lourde

Applications Claiming Priority (1)

Application Number	Priority Date	Filing Date	Title
CA002099324A CA2099324A1 (fr)	1993-06-28	1993-06-28	Faisceau de combustible pour surgenerateur ralenti a l'eau lourde

Publications (1)

Publication Number	Publication Date
CA2099324A1 true CA2099324A1 (fr)	1994-02-19

Family

ID=4151849

Family Applications (1)

Application Number	Title	Priority Date	Filing Date
CA002099324A Abandoned CA2099324A1 (fr)	1993-06-28	1993-06-28	Faisceau de combustible pour surgenerateur ralenti a l'eau lourde

Country Status (1)

Country	Link
CA (1)	CA2099324A1 (fr)

1993
- 1993-06-28 CA CA002099324A patent/CA2099324A1/fr not_active Abandoned

Legal Events

Date	Code	Title	Description
1999-06-28	FZDE	Dead

Publication	Publication Date	Title
US4393510A (en)	1983-07-12	Reactor for production of U-233
US3745069A (en)	1973-07-10	Fuel assemblies containing uo2 and puo2-uo2 for water cooled nuclear reactors
US4251321A (en)	1981-02-17	Nuclear reactor utilizing plutonium
JPH0414316B2 (fr)	1992-03-12
US3100742A (en)	1963-08-13	Fuel element for a neutronic reactor
JPH04220596A (ja)	1992-08-11	沸騰水型原子炉炉心及び沸騰水型原子炉
US4663110A (en)	1987-05-05	Fusion blanket and method for producing directly fabricable fissile fuel
US3133867A (en)	1964-05-19	Neutronic reactor fuel element
US9165691B2 (en)	2015-10-20	Burnable poison materials and apparatuses for nuclear reactors and methods of using the same
KR870006583A (ko)	1987-07-13	스펙트럴 쉬프트형 원자로와 수치환 클러스터를 사용하는 원자로의 작동방법
US4381281A (en)	1983-04-26	Reactor and process for production of novel nuclear fuel
EP0158043A1 (fr)	1985-10-16	Agencement d'un groupement de barres de contrôle
CN103943161A (zh)	2014-07-23	用于重水反应堆的多相堆芯设计和钍基燃料
US3658644A (en)	1972-04-25	Fast breeder reactor
WO1985001826A1 (fr)	1985-04-25	Reacteur nucleaire du type a germes et a couche fertile
KR910001980B1 (ko)	1991-03-30	경수형 감속 및 냉각 원자로 작동 방법 및 장치
US4362691A (en)	1982-12-07	Process of operating a nuclear reactor to minimize production of U-232
JP3062770B2 (ja)	2000-07-12	燃料集合体の構造
US4770840A (en)	1988-09-13	Spectral shift light water nuclear reactor
JPS61787A (ja)	1986-01-06	加圧水型軽水原子炉の燃料集合体
JP2006029797A (ja)	2006-02-02	核燃料集合体
CA2099324A1 (fr)	1994-02-19	Faisceau de combustible pour surgenerateur ralenti a l'eau lourde
JP2742441B2 (ja)	1998-04-22	高速増殖炉炉心
JP2006064678A (ja)	2006-03-09	原子炉の燃料集合体配置方法、燃料棒および燃料集合体
JPH05232276A (ja)	1993-09-07	原子炉の炉心