Alemberti et al., 2014 - Google Patents
Lead-cooled fast reactor (LFR) risk and safety assessment white paperAlemberti et al., 2014
View PDF- Document ID
- 18176034615182299851
- Author
- Alemberti A
- Frogheri M
- Hermsmeyer S
- Ammirabile L
- Smirnov V
- Takahashi M
- Smith C
- Wu Y
- Hwang I
- Publication year
External Links
Snippet
This paper presents the application of the Integrated Safety Assessment Methodology (ISAM), developed by the Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG), to the Lead-Cooled Fast Reactor (LFR). In this effort, the LFR-provisional …
- 238000000034 method 0 abstract description 25
Classifications
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/40—Other aspects relating to nuclear fission
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/243—Promoting flow of the coolant for liquids
- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/34—Fast breeder reactors
-
- 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
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactors
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator; Metal cooled reactors; Fast breeders
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactors
- G21C1/04—Thermal reactors; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/201—Inadequate efficiency
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2004/00—SOLUTION
- G21Y2004/40—Improving a procedure
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
-
- 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
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Alemberti et al. | Lead-cooled fast reactor (LFR) risk and safety assessment white paper | |
| Alemberti et al. | Overview of lead-cooled fast reactor activities | |
| Triplett et al. | PRISM: a competitive small modular sodium-cooled reactor | |
| Elsheikh | Safety assessment of molten salt reactors in comparison with light water reactors | |
| Alemberti et al. | European lead fast reactor—ELSY | |
| Cinotti et al. | Lead-cooled system design and challenges in the frame of Generation IV International Forum | |
| Allibert et al. | Molten salt fast reactors | |
| Shin et al. | Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation | |
| LeBlanc et al. | Integral molten salt reactor | |
| Li et al. | MELCOR severe accident analysis for a natural circulation small modular reactor | |
| Ohashi et al. | A Small‐Sized HTGR System Design for Multiple Heat Applications for Developing Countries | |
| Buongiorno | Conceptual design of a lead-bismuth cooled fast reactor with in-vessel direct-contact steam generation | |
| Orlov et al. | Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects | |
| Choi | Small modular reactors (SMRs): The case of the Republic of Korea | |
| Magan et al. | CAREM project status | |
| Roelofs | Introduction to liquid metal cooled reactors | |
| Choi et al. | URANUS: Korean lead-bismuth cooled small modular fast reactor activities | |
| Eoh et al. | Design and safety features of SALUS-100: A long fuel-cycled Sodium-cooled fast reactor | |
| Alemberti et al. | Lead-cooled fast reactor (LFR) system safety assessment | |
| Frogheri et al. | The advanced lead fast reactor European demonstrator (ALFRED) | |
| Sinha et al. | Generation-IV concepts: India | |
| Cheng | Phenomena important in liquid metal reactor simulations | |
| Yamaji et al. | Scope of conceptual development of Resilient supercritical Light water-cooled reactor (SCWR-R) | |
| Forsberg et al. | Worldwide advanced nuclear power reactors with passive and inherent safety: What, why, how, and who | |
| Todreas et al. | Flexible conversion ratio fast reactors: Overview |