Choi et al., 2007 - Google Patents
Integral effect non-loca test results for the integral type reactor SMART-P using the VISTA facilityChoi et al., 2007
View PDF- Document ID
- 8683242479139258552
- Author
- Choi K
- Park H
- Cho S
- Yi S
- Park C
- Chung M
- Publication year
External Links
Snippet
The SMART-P a pilot plant of the integral type reactor SMART (System Integrated Modular Advanced Reactor) which has new innovative design features aimed at achieving a highly enhanced safety and improved economics. A test facility (VISTA) has been constructed to …
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
- 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
- G21C17/0225—Chemical surface treatment, e.g. corrosion
-
- 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
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
- G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
- G21C19/307—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids
-
- 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
- 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
-
- 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
- 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
- G21C3/06—Casings; Jackets
-
- 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
- Y02E60/00—Enabling technologies or technologies with a potential or indirect contribution to GHG emissions mitigation
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Wang et al. | Research on thermal hydraulic behavior of small-break LOCAs in AP1000 | |
| Buongiorno et al. | Supercritical water reactor (SCWR) | |
| Hou et al. | Comparative analysis of auxiliary feedwater system and passive safety system under typical accident scenarios for integrated pressurized water reactor (IPWR) | |
| Šadek et al. | Operation and Performance Analysis of Steam | |
| Lin et al. | Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE | |
| Cheng | Safety analysis of a compact integral small light water reactor | |
| Choi et al. | Integral effect non-loca test results for the integral type reactor SMART-P using the VISTA facility | |
| Ricotti et al. | Preliminary safety analysis of the IRIS reactor | |
| KY et al. | ICONE15-10868 SAFETY-RELATED NON-LOCA SIMULATION FOR THE INTEGRAL TYPE REACTOR, SMART-P WITH THE VISTA FACILITY | |
| Ishiwatari et al. | LOCA analysis of super LWR | |
| Baek et al. | Application of the passive turbocharger to PRHRS in integral PWR type SMR with an sCO2 power cycle | |
| Choi et al. | Integral behavior of the ATLAS facility for a 3-inch small break loss of cooland accident | |
| Yang et al. | OPR1000 CEA Withdrawal at Power Accident Analysis using the SPACE code | |
| Choi et al. | Thermal Hydraulic Characteristics of the Integral Type Reactor, SMART-P for Validation of the Heat Removal Capability | |
| Helmy et al. | Analysis of break size effects on SBLOCA scenario in a 4 loop PWR using Relap5/mod 3.3 | |
| Chung et al. | EXPERIMENTAL STUDY ON THE THERMAL HYDRAULIC PHENOMENA DURING OPERATIONAL TRANSIENTS OF THE INTEGRAL TYPE REACTOR | |
| Park et al. | Experimental Study on the Intermediate Break Loss of Coolant Accident (IBLOCA) with Total failure of Safety Injection Pumps | |
| Takeda et al. | ROSA/LSTF experiment on a PWR station blackout transient with accident management measures and RELAP5 analyses | |
| CI-IOIT et al. | PARAIVIETRIC STUDIES ON THERMAL HYDRAULIC CHARACTERISTICS FOR TRANSIENT OPERATIONS OF AN INTEGRAL TYPE REACTOR | |
| Wendel et al. | Analysis of loss-of-coolant accidents in the high-flux isotope reactor | |
| Zhang et al. | Study on the Fallback Time Analysis Method for Loss of Ultimate Heat Sink Under Normal Power Operation of Nuclear Power Unit | |
| de Penguern et al. | III. PWR steam generator response to a scram at 50% load and an open grid transient (bugey-4 nuclear power plant) | |
| Park et al. | Experimental Study on the Safety Injection Pump (SIP) Failure Accompanied by the Steam Generator Tube Rupture (SGTR) | |
| Tamaki et al. | Mihama Unit 2 Steam Generator Tube Rupture Analysis | |
| Cho et al. | Simulation of an SBLOCA Test of Shutdown Cooling System Line Break with the SMARTITL Facility using the MARS-KS Code |