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automatic depressurization system (15) 15
automatic control (9) 9
blowdown (7) 7
nuclear science & technology (6) 6
scaling (6) 6
ap1000 (5) 5
bwr type reactors (5) 5
loss of coolant (5) 5
stored heat (5) 5
automation (4) 4
depressurization (4) 4
loss of coolant accident (4) 4
nuclear engineering (4) 4
sbloca (4) 4
loca (3) 3
nuclear power generation (3) 3
nuclear reactor components (3) 3
pressure dependence (3) 3
reduced-scale test (3) 3
small break (3) 3
ads (2) 2
aircraft (2) 2
automatic data processing (2) 2
automatic pilot (2) 2
control automático (2) 2
control equipment (2) 2
control systems (2) 2
control theory (2) 2
cooling (2) 2
design and construction (2) 2
downward flow cooled fuel assembly (2) 2
eccs (2) 2
engineering (2) 2
engineering instruments (2) 2
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ingeniería (2) 2
instrumentos (2) 2
instruments (2) 2
low-pressure core spray (2) 2
lwr (2) 2
maintenance and repair (2) 2
man-machine systems (2) 2
mathematical models (2) 2
models (2) 2
npp (2) 2
nuclear power plant (2) 2
nuclear power plants (2) 2
nuclear reactors (2) 2
oecd (2) 2
once-through coolant cycle (2) 2
physics (2) 2
pipe (2) 2
reactor excursion and leak analysis program (2) 2
reactor safety (2) 2
reflooding (2) 2
relap (2) 2
safety margin (2) 2
single-ended recirculation line break tests (2) 2
small break loca (2) 2
steam (2) 2
super fast reactor (2) 2
systems engineering (2) 2
technology & engineering (2) 2
ab (1) 1
aberration, chromatic and spherical (1) 1
accident investigations (1) 1
accidents (1) 1
accidents, aviation (1) 1
adaptive control systems (1) 1
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advanced pressurized reactor - 1000 mw (1) 1
advanced pressurized reactor - 600 mw (1) 1
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aeronáutica (1) 1
aeroplanes (1) 1
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air flow (1) 1
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air traffic control - automation (1) 1
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Proceedings of the Institution of Mechanical Engineers. Part I: Journal of Systems and Control Engineering, ISSN 0959-6518, 2018, Volume 233, Issue 9, pp. 1146 - 1158
This study develops a control system to automate the operation of a condensation-induced depressurization technology, which is used to achieve sub-atmospheric... 
condensation | depressurization | steam purging | Vacuum-driving flow | control system design | control system implementation | AUTOMATION & CONTROL SYSTEMS | Refilling | Vacuum chambers | Atmospheric pressure | Control systems design | Low pressure | Purging | Automatic control | Pressure reduction | Condensation
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 05/2015, Volume 49, Issue 5, pp. 852 - 857
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 07/2019, Volume 129, pp. 110 - 124
The passive safety commercial pressurized water reactors (PWRs), AP1000 and CAP1400 are equipped with the automatic depressurization system (ADS). The fourth... 
Entrainment | Passive safety | Scaling | Automatic depressurization system | Integral effect test | SYSTEM | ADS-4 | AP1000 | LIQUID ENTRAINMENT | OF-COOLANT-ACCIDENT | MODEL | PIPE | SMALL BREAK LOCA | PHASE | NUCLEAR SCIENCE & TECHNOLOGY | Safety regulations | Analysis
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 04/2012, Volume 46, Issue 4, pp. 410 - 415
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 08/2015, Volume 49, Issue 8, pp. 1399 - 1404
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 02/2017, Volume 100, pp. 169 - 177
The AP1000 nuclear power plant safety system is characterized by its unique passive Emergency Core Cooling System (ECCS), including Core Makeup Tanks (CMTs),... 
SBLOCA | AP1000 | Automatic Depressurization System | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear energy | Models | Nuclear power plants | Automation | Sensitivity analysis | Cooling | Tanks | Water tanks | Nuclear reactor components | Nuclear engineering | Nuclear power generation
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 2011, Volume 241, Issue 4, pp. 1152 - 1164
Advanced nuclear water reactors rely on containment behaviour in realization of some of their passive safety functions. Steam condensation on containment... 
DD | EPRI | LOCA | Long-term gravity make-up system | EHRS | Organization for economic co-operation and development | PCCS | Large break LOCA | Advanced pressurized reactor - 600 MW | Reactor vessel | ISP-42 | Nuclear energy agency | ADS | Quench tank | Auxiliary building | PAssive Nachwärmeabfuhr- und DruckAbbau-testanlange (passive decay heat removal and depressurization test facility) | DW | OECD | Advanced pressurized reactor - 1000 MW | SBLOCA | BWR | AP600 | Emergency heat removal system | Reactor excursion and leak analysis program | Thermal/hydraulic | AB | QT | SIET | Droplets diameter | LWR | Pressure suppression system | Emergency boration tank | Heat transfer coefficient | Nuclear regulatory commission | IRIS | PSS | RC | Boiling water reactor | Chemical volume and control system | Phenomena identification and ranking table | Societ Informazioni Esperienze Termoidrauliche (company for information on thermal-hydraulic experimentation) | Generation of thermal-hydraulic information for containments | Nuclear power plant | HTC | CVCS | PANDA | RWST | LGMS | RV | Safety analysis report | SAR | Refuelling water storage tank | RELAP | SBWR | T/H | Small break LOCA | Direct vessel injection | NPP | Reactor cavity | Dry-well | EBT | Simulatore Per Esperienze di Sicurezza (simulator for safety tests) | GOTHIC | PIRT | LBLOCA | Loss of coolant accident | AP1000 | Passive containment cooling system | Automatic depressurization system | NEA | SPES | Light water reactor | International reactor innovative and secure | Electric power research institute | DVI | Simplified boiling water reactor | International standard problem number 42 | NRC | NONCONDENSABLE GASES | REACTOR | CONDENSATION HEAT-TRANSFER | NUCLEAR SCIENCE & TECHNOLOGY | STEAM | AP600 CONTAINMENT | VERTICAL TUBE | Nuclear reactor components | Nuclear engineering | Mathematical models | Droplets | Models | Modelling | Nuclear reactors | Containment
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 10/2011, Volume 48, Issue 10, pp. 1289 - 1299
This paper describes loss of coolant accident (LOCA) analyses of the Supercritical-pressure Water-Cooled Fast Reactor (Super Fast Reactor). The features of the... 
depressurization | automatic depressurization system | reflooding | Super Fast Reactor | downward flow cooled fuel assembly | low-pressure core spray | once-through coolant cycle | loss of coolant accident | blowdown | Data reconciliation | Gross error detection | Nuclear material accounting | Reprocessing | Safeguards | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 2011, Volume 48, Issue 10, pp. 1289 - 1299
This paper describes loss of coolant accident (LOCA) analyses of the Supercritical-pressure Water-Cooled Fast Reactor (Super Fast Reactor). The features of the... 
Blowdown | Once-through coolant cycle | Loss of coolant accident | Reflooding | Super Fast Reactor | Automatic depressurization system | Low-pressure core spray | Depressurization | Downward flow cooled fuel assembly | Nuclear safety | LOCA | Nuclear engineering | Nuclear reactor components | Nuclear power generation | Nuclear reactors | Fuels | Density
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 2011, Volume 241, Issue 4, pp. 1137 - 1144
Accurate simulation of transient system behavior of a nuclear power plant is the goal of systems code calculations, and the evaluation of a code's calculation... 
CHF | Lower Plenum | SESAR | LOCA | Loss of Coolant Accident | Multi-Application Small Light-Water Reactor | SESAR Thermal Hydraulics | ADS | Purdue Advanced Reactor Core Simulator | OECD | IAEA | Reactor Excursion and Leak Analysis Program | Reactor Pressure Vessel | SBLOCA | Main Steam | PRZ | Small Break Loss of Coolant Accident | International Collaborative Standard Problem | Nuclear Steam Supply System | Critical Heat Flux | LWR | Upper Plenum | Pressurized Water Reactor | MASLWR | PWR | PKL | Natural Circulation | PARCS | Symbolic Nuclear Analysis Package | TRAC/RELAP Advanced Computational Engine | HPC | Automatic Depressurization System | High Pressure Containment | Pressurizer | NSSS | Cold Leg | RELAP | NPP | ROSA/LSTF | RHRS | Primä rkreisläufe (Test Facility) | ICSP | U.S. Nuclear Regulatory Commission | RPV | Oregon State University | Nuclear Power Plant | Light-Water Reactor | SETH | TRACE | Senior Group of Experts on Nuclear Safety Research | Organization for Economic Cooperation and Development | Hot Leg | International Atomic Energy Agency | SNAP | OSU | Residual Heat Removal System | USNRC | Feed Water | ROSA Large Scale Test Facility | Steam Generator | NUCLEAR SCIENCE & TECHNOLOGY | Computational fluid dynamics | Coiling | Nuclear engineering | Helical | Numerical control | Nuclear power generation | Mathematical models | Assessments
Journal Article
International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, Volume 10, pp. 8630 - 8642
Conference Proceeding
Journal of Nuclear Science and Technology, ISSN 0022-3131, 09/1984, Volume 21, Issue 9, pp. 714 - 721
Scaling considerations have been made for liquid line small break simulation tests of a BWR affected by the stored heat released from loop structures.... 
BWR type reactors | reduced-scale test | automatic depressurization system | scaling | small break | loss of coolant | pressure dependence | stored heat | blowdown | Blowdown | Pressure dependence | Stored heat | Loss of coolant | Small break | Automatic depressurization system | Scaling | Reduced-scale test
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 04/1985, Volume 22, Issue 4, pp. 249 - 268
Integral blowdown refill/reflood tests have been made at the Two Bundle Loop (TBL) to clarify the BWR safety margin for the Emergency Core Cooling System... 
BWR type reactors | automatic depressurization system | scaling | safety margin | reactor safety | loss of coolant | single-ended recirculation line break tests | stored heat | ECCS | blowdown | Blowdown | Stored heat | Reactor safety | Loss of coolant | Safety margin | Automatic depressurization system | Scaling | Single-ended recirculation line break tests
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 1984, Volume 21, Issue 9, pp. 714 - 721
Scaling considerations have been made for liquid line small break simulation tests of a BWR affected by the stored heat released from loop structures.... 
BWR type reactors | reduced-scale test | automatic depressurization system | scaling | small break | loss of coolant | pressure dependence | stored heat | blowdown
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 1985, Volume 22, Issue 4, pp. 249 - 268
Integral blowdown refill/reflood tests have been made at the Two Bundle Loop (TBL) to clarify the BWR safety margin for the Emergency Core Cooling System... 
BWR type reactors | automatic depressurization system | scaling | safety mar-gin | reactor safety | loss of coolant | single-ended recirculation line break tests | stored heat | ECCS | blowdown | safety margin
Journal Article
Modeling, Identification and Control, ISSN 0332-7353, 1997, Volume 18, Issue 1, pp. 61 - 73
Dynamic simulators for pipelines with multiphase flow have proved to be important computational tools for both design and operational support of oil and gas... 
Depressurization | Severe slugging | Slug tracking | depressurization | OPERATIONS RESEARCH & MANAGEMENT SCIENCE | severe slugging | ROBOTICS & AUTOMATIC CONTROL | K AC ROBOTICS & AUTOMATIC CONTROL | slug tracking | K PE OPERATIONS RESEARCH & MANAGEMENT SCIENCE
Journal Article
Work, ISSN 1051-9815, 2012, Volume 41, Issue 1, pp. 222 - 224
The probes allow the pilot to control the aircraft speed was essential to the balance of the flight. Opinions of experts who claim that "the design of the... 
human error | processing information | trainning | PUBLIC, ENVIRONMENTAL & OCCUPATIONAL HEALTH | Accidents, Aviation | Man-Machine Systems | Aircraft | Equipment Failure Analysis | Automatic Data Processing
Journal Article
IEEE Transactions on Nuclear Science, ISSN 0018-9499, 02/1998, Volume 45, Issue 1, pp. 17 - 29
Journal Article
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