Presentation is loading. Please wait.

Presentation is loading. Please wait.

Advanced Test Reactor.

Published byCaroline Hubbard Modified over 9 years ago

Similar presentations

Presentation on theme: "Advanced Test Reactor."— Presentation transcript:

1 Advanced Test Reactor

2 ATR vs Commercial Reactor
Confinement Structure Operating Conditions 390 psi 140 degrees F Reactor Core 4 feet x 4 feet 880 pounds 21 pounds of uranium Containment Structure Operating Conditions 2600 psi 550 degrees F Reactor Core 12 feet x 15 feet 154 tons 12,000 pounds of uranium

3 ATR Timeline 1967 1987 1997 2007 Start of Operations (6 loops 1967)
2nd Core Internals Changeout (CIC) 1977 9th Loop Facility Installed, Improved Loop Capabilities 1980 Lead Experiment Facility Installed 1984 Reactor Control Room Replaced 1989 3rd Core Internal 1986 Process Control Room Replaced & Core Reconfigured 1993 Loop Control System Replaced & 4th Core Internal Decreased Active Loops to 5 1994 External Secondary Piping & Cooling Tower Replacement 1998 Irradiation Test Vehicle (ITV) Installed 1999 5th Core Internal 2004 6th Core Internal 2010 1967 1987 1997 2007 1st Core Internals Changeout (CIC) 1972 Increased number of loops from 6 to 8 1973 Plant Protective System Upgrade 2006

4 ATR Specifications Reactor Type
Pressurized, light-water moderated and cooled, beryllium reflector Reactor Vessel 3.65 m diameter cylinder, m high Stainless steel Reactor Core 1.22 m (diameter & height) 40 fuel elements, high enriched U-235

5 ATR Specifications (continued)
Coolant Inlet Temperature & Pressure 52°C, 2450 kPa Thermal Power & Flux Maximum Total Core Power – 250MW Approximate Peak Flux Values (Unperturbed) 1 x n/cm2–sec thermal 5 x n/cm2-sec fast

6 ATR Specifications (continued)
Hafnium Reactivity Control Drums/Rods Maintains Axial Flux Shape During Operating Cycle Flux/Power Adjustments Among Core Lobes/Flux Traps Irradiation Facilities 77 Reflector Positions 68 Flux Traps 4 In-pile Tubes 5

7 South and East Flux Trap Irradiation Facilities
ATR Core Cross Section b Outer Shim Control Cylinder “B” Position Fuel Element Neck Shim Rod (1-6 Typical) MICE Inboard “A” Position (1-8) Outboard “A” Position (9-16) Standard Loop Irradiation Facility “I” Position Outer South Irradiation Tank South and East Flux Trap Irradiation Facilities Safety Rod “H” Position Large Loop Irradiation Facility ITV Outer North Irradiation Tank H9 H1 H5 H13 H8 H7 H6 H11 H10 H12 H15 H14 H16 H2 H3 H4 3 1 2 4 5 7 6 M-1 M-3 M-2

8 ATR Vessel & Internals

9 Irradiation Test Vehicle

10 ATR Standard Loop Layout
Loop Closure Plugs Line Heaters Pressurizer Heat Exchanger Reactor Core Ion Exchange Columns Pumps Loop Inlet and Outlet Piping Operating Console

Download ppt "Advanced Test Reactor."

Similar presentations

INRNE-BAS MELCOR Pre -Test Calculation of Boil-off test at Quench facility 11th International QUENCH Workshop Forschungszentrum Karlsruhe (FZK), October.

INRNE-BAS MELCOR Pre -Test Calculation of Boil-off test at Quench facility 11th International QUENCH Workshop Forschungszentrum Karlsruhe (FZK), October.
Nuclear Power Turkey Point Power Plant Process. Turkey Point Power Plant Built on 12, 700 acres in Homestead Opened in 1972 Cost to build both reactors.

Nuclear Power Turkey Point Power Plant Process. Turkey Point Power Plant Built on 12, 700 acres in Homestead Opened in 1972 Cost to build both reactors.
Lesson 17 HEAT GENERATION

Lesson 17 HEAT GENERATION
Relevant Thermal-Hydraulic Aspects in the Design of the RRR A. Doval, C. Mazufri F.P. Moreno 1089 8400- Bariloche, Rio Negro, Argentina.

Relevant Thermal-Hydraulic Aspects in the Design of the RRR A. Doval, C. Mazufri F.P. Moreno Bariloche, Rio Negro, Argentina.
Www.inl.gov 3 rd Advanced Graphite Creep Capsule (AGC-3) Irradiation Proceedings of the 2013 14 th International Nuclear Graphite Specialists Meeting INGSM-14.

3 rd Advanced Graphite Creep Capsule (AGC-3) Irradiation Proceedings of the th International Nuclear Graphite Specialists Meeting INGSM-14.
Www.inl.gov Preliminary Results of the AGC-3 Irradiation in the Advanced Test Reactor and Design of AGC-4 Proceedings of the 2014 15 th International Nuclear.

Preliminary Results of the AGC-3 Irradiation in the Advanced Test Reactor and Design of AGC-4 Proceedings of the th International Nuclear.
PHYSICS DESIGN OF 30 MW MULTI PURPOSE RESEARCH REACTOR Archana Sharma Research Reactor Services Division BHABHA ATOMIC RESEARCH CENTRE, INDIA.

PHYSICS DESIGN OF 30 MW MULTI PURPOSE RESEARCH REACTOR Archana Sharma Research Reactor Services Division BHABHA ATOMIC RESEARCH CENTRE, INDIA.
Thermal-Hydraulic Transient Analysis of the Missouri University Research Reactor (MURR) TRTR Annual Meeting September 17-20, 2007 Dr. Robert C. Nelson1,

Thermal-Hydraulic Transient Analysis of the Missouri University Research Reactor (MURR) TRTR Annual Meeting September 17-20, 2007 Dr. Robert C. Nelson1,
Some nuc. reactors. Nuclear reaction by Fission Nuclear fission: All commercial power reactors are based on nuclear fission. generally use uranium and.

Some nuc. reactors. Nuclear reaction by Fission Nuclear fission: All commercial power reactors are based on nuclear fission. generally use uranium and.
The Harnessed Atom Lesson Six Atoms to Electricity.

The Harnessed Atom Lesson Six Atoms to Electricity.
EUROTRANS – DM1 RELAP5 Model Evaluation with SIMMER-III Code and Preliminary Transient Analysis for EFIT Reactor WP5.1 Progress Meeting KTH / Stockholm,

EUROTRANS – DM1 RELAP5 Model Evaluation with SIMMER-III Code and Preliminary Transient Analysis for EFIT Reactor WP5.1 Progress Meeting KTH / Stockholm,
Characterization of the Engineering Test Reactor at the INL for Final Disposition TRTR 2007 J. R. Parry Irradiation Test Programs INL.

Characterization of the Engineering Test Reactor at the INL for Final Disposition TRTR 2007 J. R. Parry Irradiation Test Programs INL.
Www.inl.gov HTTF Analyses Using RELAP5-3D Paul D. Bayless RELAP5 International Users Seminar September 2010.

HTTF Analyses Using RELAP5-3D Paul D. Bayless RELAP5 International Users Seminar September 2010.
Www.inl.gov Thermal-Hydraulic Analysis Results of a Seismically-Induced Loss of Coolant Accident Involving Experiment Out-of-Pile Loop Piping at the Idaho.

Thermal-Hydraulic Analysis Results of a Seismically-Induced Loss of Coolant Accident Involving Experiment Out-of-Pile Loop Piping at the Idaho.
Dakota Nickerson, Kyle Pflueger, Adam Leschber, Andrew Dahlke M.E. Undergrad 1.

Dakota Nickerson, Kyle Pflueger, Adam Leschber, Andrew Dahlke M.E. Undergrad 1.
Dakota Nickerson, Kyle Pflueger, Adam Leschber, Andrew Dahlke M.E. Undergrad 1.

Dakota Nickerson, Kyle Pflueger, Adam Leschber, Andrew Dahlke M.E. Undergrad 1.
1 Acetone, 2-Propanol H 2 Acetone 2-Propanol L2 Acetone, 2-Propanol L201 L101L1 L3 L4 L10 L9 Condenser Reboiler Distillation Column Endothermic Reactor.

1 Acetone, 2-Propanol H 2 Acetone 2-Propanol L2 Acetone, 2-Propanol L201 L101L1 L3 L4 L10 L9 Condenser Reboiler Distillation Column Endothermic Reactor.
NUCLEAR SAFETY Barbora Svobodová Angličtina-odborná II.

NUCLEAR SAFETY Barbora Svobodová Angličtina-odborná II.
STEAM HEATING.

STEAM HEATING.
 A nuclear reactor produces and controls the release of energy from splitting the atoms of certain elements. In a nuclear power reactor, the energy released.

 A nuclear reactor produces and controls the release of energy from splitting the atoms of certain elements. In a nuclear power reactor, the energy released.

Similar presentations

Ads by Google