SE9904316L - Procedure for operating a nuclear plant - Google Patents
Procedure for operating a nuclear plantInfo
- Publication number
- SE9904316L SE9904316L SE9904316A SE9904316A SE9904316L SE 9904316 L SE9904316 L SE 9904316L SE 9904316 A SE9904316 A SE 9904316A SE 9904316 A SE9904316 A SE 9904316A SE 9904316 L SE9904316 L SE 9904316L
- Authority
- SE
- Sweden
- Prior art keywords
- fuel
- primary
- nuclear
- question
- unit
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
-
- 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
-
- 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)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention concerns a method for operating a nuclear plant comprising a reactor with a set of fuel assemblies each comprising a number of fuel units. Each fuel unit comprises at least one cladding member, arranged to enclose a nuclear fuel so that a gap is formed between the nuclear fuel and the cladding member. The method comprises the steps of establishing a primary fuel defect of one of said fuel units, determining the value of a first primary parameter regarding the burn-up degree of the nuclear fuel of the fuel unit in question, the value of a second primary parameter regarding effect history for the fuel unit in question, the value of a third primary parameter regarding the size of said gap of the fuel unit in question, and calculating the development of the primary fuel defect and of future leakage of nuclear fuel from the fuel unit in question with regard to said primary parameters.
Priority Applications (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
SE9904316A SE514803C2 (en) | 1999-11-29 | 1999-11-29 | Procedure for operating a nuclear plant |
AU19108/01A AU1910801A (en) | 1999-11-29 | 2000-11-29 | A method for operating a nuclear plant |
PCT/SE2000/002377 WO2001039207A1 (en) | 1999-11-29 | 2000-11-29 | A method for operating a nuclear plant |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
SE9904316A SE514803C2 (en) | 1999-11-29 | 1999-11-29 | Procedure for operating a nuclear plant |
Publications (3)
Publication Number | Publication Date |
---|---|
SE9904316D0 SE9904316D0 (en) | 1999-11-29 |
SE9904316L true SE9904316L (en) | 2001-04-30 |
SE514803C2 SE514803C2 (en) | 2001-04-30 |
Family
ID=20417890
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
SE9904316A SE514803C2 (en) | 1999-11-29 | 1999-11-29 | Procedure for operating a nuclear plant |
Country Status (3)
Country | Link |
---|---|
AU (1) | AU1910801A (en) |
SE (1) | SE514803C2 (en) |
WO (1) | WO2001039207A1 (en) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2858103B1 (en) * | 2003-07-25 | 2005-10-21 | Framatome Anp | METHOD FOR ESTIMATING THE NUMBER OF NON-WATER PENES PRESENT IN NUCLEAR FUEL ASSEMBLIES, DEVICE AND SUPPORT USED IN A CORRESPONDING COMPUTER |
SE527796C2 (en) * | 2004-06-14 | 2006-06-07 | Westinghouse Electric Sweden | Process for operating a reactor at a nuclear plant |
US8737557B2 (en) | 2006-07-21 | 2014-05-27 | Areva Inc. | Method for prediction of light water reactor fuel defects using a fuel condition index |
SE532638C2 (en) | 2008-06-04 | 2010-03-09 | Westinghouse Electric Sweden | Method and apparatus for monitoring the operation of a nuclear reactor |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS56132594A (en) * | 1980-03-19 | 1981-10-16 | Hitachi Ltd | Monitoring system for grasping core state at accident |
US5537450A (en) * | 1994-01-31 | 1996-07-16 | Radiological & Chemical Technology, Inc. | On-line analysis of fuel integrity |
SE514184C2 (en) * | 1997-11-21 | 2001-01-22 | Asea Atom Ab | Method and apparatus for evaluating the integrity of nuclear fuel in a nuclear plant |
-
1999
- 1999-11-29 SE SE9904316A patent/SE514803C2/en not_active IP Right Cessation
-
2000
- 2000-11-29 AU AU19108/01A patent/AU1910801A/en not_active Abandoned
- 2000-11-29 WO PCT/SE2000/002377 patent/WO2001039207A1/en active Application Filing
Also Published As
Publication number | Publication date |
---|---|
AU1910801A (en) | 2001-06-04 |
WO2001039207A1 (en) | 2001-05-31 |
SE9904316D0 (en) | 1999-11-29 |
SE514803C2 (en) | 2001-04-30 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
WO1995003614A3 (en) | System for automatic refueling of a nuclear reactor | |
SE9904316L (en) | Procedure for operating a nuclear plant | |
Asada et al. | System based code: Principal concept | |
DE602004022322D1 (en) | FUEL ASSEMBLY FOR A PRESSURE WATER CORE REACTOR WITH PLUTONIUM-FREE ENRICHED URAN | |
Pulkkinen et al. | An expert panel approach to support risk-informed decision making | |
Wu et al. | Risk-based inspection and maintenance in process plants and their practices in Taiwan | |
CN113627612B (en) | Power technology supervision method for electrical equipment in nuclear island and computer terminal | |
Zhou et al. | Construction of an East Asia Nuclear Security System | |
Bugaenko et al. | Management of the service life of a nuclear Power Plant | |
Käufer | Regulatory and safety aspects of ageing in nuclear power plants | |
Garrick | Risk Management of the Nuclear Power Industry | |
Serkov et al. | Industry safety inspection of hydraulic structures of electric power stations under conditions of the development of market relations and transformation of organizational and legal forms of power enterprises | |
Katona | The Paks Nuclear Power Plant: scientific inventions-practical applications | |
Yang et al. | Analysis for Risk informed decision-making regarding emergent issues relevant to nuclear power plants | |
Chang et al. | Comparative Study on NPP Commissioning and Operation Requirements between IAEA and Korea | |
Hugo | Work Domain Analysis and Operational Concepts for Advanced Nuclear Power Plants | |
Roche | French administrative practice and design codes for nuclear vessels | |
Rahimi et al. | State estimation issues: External system modeling enhancements. Volume 1: External system modeling guidelines; Final report | |
Corney | The economic and political significance of Russia's RBMK reactors | |
Bain et al. | Restart Testing Program for piping following steam generator replacement at North Anna Unit 1 | |
Levy | Decision support for the management of aging nuclear critical infrastructures: vulnerability assessment and multi-criteria decision analysis | |
CN108492900A (en) | The interface method and system of PWR nuclear power plant failure regulation and accident treatment code | |
Newberry et al. | Regulatory perspectives of license renewal | |
Laue et al. | Role and demonstration of structural integrity of LMFBR structures within the frame of the safety assessment process | |
Gillette | Nuclear Energy Crisis in the Former Soviet Union: Will the Nuclear Energy Protocol of the European Energy Charter Provide the Necessary Solutions |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
NUG | Patent has lapsed |