CA2724582A1 - Combustible pour reacteur a eau lourde ou reacteur a graphite et son procede de production - Google Patents
Combustible pour reacteur a eau lourde ou reacteur a graphite et son procede de production Download PDFInfo
- Publication number
- CA2724582A1 CA2724582A1 CA2724582A CA2724582A CA2724582A1 CA 2724582 A1 CA2724582 A1 CA 2724582A1 CA 2724582 A CA2724582 A CA 2724582A CA 2724582 A CA2724582 A CA 2724582A CA 2724582 A1 CA2724582 A1 CA 2724582A1
- Authority
- CA
- Canada
- Prior art keywords
- fuel
- reactor
- uranium
- reprocessed
- value
- Prior art date
- 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
Links
Classifications
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
PCT/JP2008/060569 WO2009150710A1 (fr) | 2008-06-09 | 2008-06-09 | Combustible pour réacteur à eau lourde ou réacteur à graphite et son procédé de production |
Publications (1)
Publication Number | Publication Date |
---|---|
CA2724582A1 true CA2724582A1 (fr) | 2009-12-17 |
Family
ID=41416435
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CA2724582A Abandoned CA2724582A1 (fr) | 2008-06-09 | 2008-06-09 | Combustible pour reacteur a eau lourde ou reacteur a graphite et son procede de production |
Country Status (3)
Country | Link |
---|---|
KR (1) | KR101488555B1 (fr) |
CA (1) | CA2724582A1 (fr) |
WO (1) | WO2009150710A1 (fr) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2011142869A2 (fr) * | 2010-02-22 | 2011-11-17 | Advanced Reactor Concepts LLC | Petite centrale nucléaire à neutrons rapides avec un long intervalle de rechargement |
CN108962417B (zh) * | 2018-06-22 | 2020-02-21 | 中核核电运行管理有限公司 | 重水堆钴同位素生产方法 |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP3008129B2 (ja) * | 1990-11-29 | 2000-02-14 | 株式会社日立製作所 | 燃料集合体の製造方法 |
US5475723A (en) * | 1994-03-21 | 1995-12-12 | General Electric Company | Nuclear fuel cladding with hydrogen absorbing inner liner |
TW258815B (en) * | 1994-07-13 | 1995-10-01 | Gen Electric | Nuclear fuel cladding having a gold coating |
JP3325462B2 (ja) * | 1996-06-04 | 2002-09-17 | 核燃料サイクル開発機構 | 燃料集合体の製造方法 |
JP2000292575A (ja) * | 1999-04-08 | 2000-10-20 | Hitachi Ltd | 燃料集合体 |
-
2008
- 2008-06-09 CA CA2724582A patent/CA2724582A1/fr not_active Abandoned
- 2008-06-09 WO PCT/JP2008/060569 patent/WO2009150710A1/fr active Application Filing
- 2008-06-09 KR KR1020107028123A patent/KR101488555B1/ko active IP Right Grant
Also Published As
Publication number | Publication date |
---|---|
KR20110070962A (ko) | 2011-06-27 |
KR101488555B1 (ko) | 2015-02-02 |
WO2009150710A1 (fr) | 2009-12-17 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Shwageraus et al. | Use of thorium for transmutation of plutonium and minor actinides in PWRs | |
Kabach et al. | A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor | |
ZA200208184B (en) | Method of incineration of minor actinides in nuclear reactors. | |
CA2724582A1 (fr) | Combustible pour reacteur a eau lourde ou reacteur a graphite et son procede de production | |
Gentry et al. | A neutronic investigation of the use of fully ceramic microencapsulated fuel for Pu/Np burning in PWRs | |
Rajagukguk et al. | Neutronic calculation for PWR MOX fuel pin cells with WIMSD-5B code | |
Alhaj et al. | Partial loading of thorium-plutonium fuel in a pressurized water reactor | |
Susilo et al. | Fuel burn-up distribution and transuranic nuclide contents produced at the first cycle operation of AP1000 | |
Ganda et al. | Plutonium recycling in hydride fueled PWR cores | |
US12112857B2 (en) | Light water reactor uranium fuel assembly and operation method of nuclear fuel cycle | |
RU2791731C1 (ru) | Урановая тепловыделяющая сборка легководного реактора и способ функционирования ядерного топливного цикла | |
Susilo et al. | Irradiation characteristic of natural Uo2 pin PHWR target at PRTF of RSG–Gas Core | |
Yamamoto et al. | Analysis of core physics experiments on fresh and irradiated PWR UO2 fuels in the REBUS program | |
Powers et al. | Fully Ceramic Microencapsulated Fuels: Characteristics and Potential LWR Applications | |
da Silva et al. | Neutronic evaluation of CANDU-6 core using reprocessed fuels | |
Hoffman | Preliminary report on blending strategies for inert-matrix fuel recycling in LWRs. | |
Radulescu et al. | Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel | |
Nabila et al. | An Attempt to Find the Optimal Loading Pattern of Minor Actinides in the PWR Core | |
Ginex et al. | One-dimensional neutronic analysis of BWR hydride fuel bundles | |
Lovasic et al. | International Atomic Energy Agency (IAEA) Activity on Technical Influence of High Burnup UOX and MOX Water Reactor Fuel on Spent Fuel Management–9065, WM2009 Conference | |
EL-Khawlania et al. | Burn up Analysis for Fuel Assembly Unit in a Pressurized Heavy Water CANDU Reactor | |
Breza et al. | Advanced fuel cycles options for LWRs and IMF benchmark definition | |
Schaechter et al. | Method with improved accuracy for the determination of nuclear fuel burnup using burnable poisons | |
Yamamoto et al. | A study on the criticality safety for the direct disposal of used nuclear fuel in Japan: Application of burnup credit to the criticality safety evaluation for the disposal canister-14049 | |
Porsch et al. | Advanced PWR Core Design with Siemens High-Plutonium-Content MOX Fuel Assemblies |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
EEER | Examination request |
Effective date: 20130308 |
|
FZDE | Dead |
Effective date: 20150609 |