Presentation is loading. Please wait.

Presentation is loading. Please wait. 3 rd Advanced Graphite Creep Capsule (AGC-3) Irradiation Proceedings of the 2013 14 th International Nuclear Graphite Specialists Meeting INGSM-14.

Similar presentations

Presentation on theme: " 3 rd Advanced Graphite Creep Capsule (AGC-3) Irradiation Proceedings of the 2013 14 th International Nuclear Graphite Specialists Meeting INGSM-14."— Presentation transcript:

1 3 rd Advanced Graphite Creep Capsule (AGC-3) Irradiation Proceedings of the 2013 14 th International Nuclear Graphite Specialists Meeting INGSM-14 September 16 – 18, 2013, Seattle, Wa. USA

2 Agenda Graphite irradiation overview Advanced Test Reactor (ATR) irradiation locations and details Graphite specimens Capsule and test train design Control and monitoring systems AGC-3 Experiment – Design – Irradiation Summary ATR Core During Reactor Operation 2

3 Graphite Irradiation Experiments Graphite material property database Irradiation creep Thermal changes Mechanical changes Physical changes High dose tensile irradiation creep studies needed for pebble bed design Database for previous nuclear graphite grades 900 ºC 1200 ºC AGC - 2 600 ºC 1500 ºC AGC - 1 AGC - 4 AGC - 6 Dose (dpa) 13 4.5 6 HTV-1HTV-2 AGC - 3 AGC - 5 Historic nuclear grade graphites are no longer available due to loss of feedstock ATR experiments to be irradiated: – 600, 900 and 1200ºC – Up to 4 or 7 dpa (5.5 and 9.6 × 10 21 n/cm 2 for E > 0.1 MeV) AGC-1 was irradiated from September 2009 to January 2011 AGC-2 was irradiated from April 2011 to May 2012 AGC-3 will be irradiated from November 2012 to March 2014 3

4 AGC-1 and AGC-2 were irradiated in the South Flux Trap position AGC-3 is being irradiated in the East Flux Trap of the ATR Use of ATR Flux Trap – Maximizes number of graphite specimens, stacks/channels, loads, and combinations – Flux rate minimizes irradiation time to meet NGNP program schedule Test trains rotated to minimize flux gradient across diameter Most of ATR core height (44” of 48”) used to maximize specimen numbers and provide spectrum of fast fluence damage levels AGC Experiment Locations Fuel Elements South Flux Trap Location for AGC-1 & 2 North H Positions I Positions Small B Position Control Drum ATR Core Cross Section East Flux Trap Location for AGC-3 4

5 Some large and small specimens – Large – Ø ½” (12.3 mm) × 1” (25.4 mm) tall – Small – Ø ½” (12.3 mm) × ¼” (6.4 mm) tall New ‘intermediate’ size specimen container – Ø ½” (12.3 mm) × ½” (12.7 mm) tall 6 Perimeter Stacks – 18 large size specimens above core center – 18 large and 3 small size specimens below core center Center Stack – 152 small and 9 intermediate size specimens Flux wires in spacers between graphite specimens Core Centerline Full Size Unloaded Specimens Compressive Load Push Rod Unloaded Small Specimens Loaded Large Specimens AGC-3 Graphite Specimens Flux Monitor Spacer Small Specimen Large Specimen AGC-2 Specimen Stack 5

6 AGC-3 Irradiation Requirements 900ºC design temperature Fast neutron damage up to 3 to 4 dpa Compressive loads on specimens – 2 stacks with 2 ksi (14 MPa) compressive load – 2 stacks with 2.5 ksi (17 MPa) compressive load – 2 stacks with 3 ksi (21 MPa) compressive load Loaded and unloaded companion specimens Lift specimens during reactor outages to verify specimen load condition Grab samples of temperature control gas to monitor for oxidation of specimens AGC Being Inserted into the ATR AGC Experiment ATR Top Head 6

7 AGC Capsule Design Features 6 specimen stacks around capsule perimeter with compressive load on upper half of stack 7 th specimen stack in center without compressive load Graphite holder to contain graphite specimen stacks and thermocouples (TCs) 12 TC locations with positions located throughout core height Insulating gas jacket to attain desired temperature Radiation heat shield to limit radiation heat transfer AGC Capsule Cross Section ThermocouplesSpecimen Holder Graphite Specimens Heat Shield/Gas Jacket Area Temperature Control Gas Line Lower Bellows Gas Line 7

8 Temperature Control Utilize neutron capture and gamma heating of specimens as heat source Manipulate temperature by adjusting ratio of conducting and insulating gases in insulating gas gap AGC irradiations use He and Ar to maximize control band for temperature control All AGC experiments utilize same temperature control system Distributed control system used for control and data collection 8

9 Pneumatic rams provide compressive load on specimens in six peripheral stacks located above the ATR core centerline – no load on specimens below core centerline Load cells between pneumatic rams and push bars to monitor specimen load Push bars translate and transmit compressive load to push rods located in smaller circle directly over specimen stacks – Stainless steel push rods transition to graphite in higher temperature areas of experiment Gas bellows below core to lift top specimens during outages to verify load conditions – Position indicators attached to push bars to verify specimen movement during outages Compressive loads imposed on diametrically opposite specimen stack pairs to avoid eccentrically loading the graphite holder AGC Test Train Push RodPneumatic Ram Gas Bellows Load Cell Position Indicators Push Bar Graphite Specimens Compressive Load System 9

10 AGC-2 Design Changes/Improvements TC Pair Locations in AGC-2 TC Locations TC12 moved to same elevation as TC9 to provide temperature gradient across the whole experiment Replaced stainless steel with aluminum in some internal components to reduce weight – Load cell adapter, plates, push bars and sleeves Tungsten ‘gamma heaters’ added to top and bottom of center channel Zirconia gamma heaters added to the bottom of peripheral channels Removed spacers in specimen stacks to increase number of specimens – 36 large and 14 to 18 small specimens in peripheral stacks (vs. 29 and 14) – 170 (vs. 172) small specimens in center stack due to tungsten heaters 10

11 East Flux Trap vs. South Flux Trap – 15% lower nominal power – 20% power variation versus 10% for AGC-1 and AGC-2 Increased specimen creep from higher design temperature (900ºC) – Slightly smaller diameter specimens – Additional stroke in pneumatic cylinders – Additional room at core center for creep in specimens and housing Elevated mean wall temperature in pressure boundary from higher temperature Five zones versus single vertical temperature control zone – Significantly enhanced temperature control – Significantly improved axial temperature distribution Different gamma ‘heaters’ – Molybdenum vs. tungsten and zirconia AGC-3 Design Challenges and Changes AGC Capsule Cross Section Thermocouple s Specimen Holder Graphite Specimens Heat Shield/Gas Jacket Area Temperature Control Gas Line Lower Bellows Gas Line 11

12 Lower Gas Bellows installed on test train Outer shell with gas bellows installed inside Gas Bellows before installation in outer shell Design initiated – April 2011 Final design reviews – March 2012 Test train inserted in ATR – August 2012 Start of irradiation – November 2012 – Moisture level during start-up – Excellent temperature control – Extremely flat axial temperature profile – Compressive load control system leakage – Helium shortage – Loads reduced on stacks 2 and 5 to replace/supplement stacks 1 and 4 End of first irradiation cycle – January 2013 – Accumulated 51 EFPDs – Peak fast neutron damage – 1.0 dpa Removed for short high power operating cycle – January 2013 Re-insertion in ATR – July 2013 Irradiation complete – March 2014 AGC-3 Schedule and Status 12

13 Temperatures During Irradiation 13

14 Compressive Loads During Irradiation 14

15 AGC-3 Experiment Multiple design improvements and lessons learned from AGC-1 and AGC-2 incorporated New design challenges from increased temperature and new irradiation position Irradiation started in November 2012 – Significant improvement in temperature control and axial temperature profile – Compressive load control system leakage – Accumulated 51 EFPDs – Peak fast neutron damage level – 1.0 dpa Removed in January 2013 with re-insertion completed in July 2013 Irradiation complete in March 2014 AGC Experiment Installed in ATR Summary AGC Test Train ATR Core ATR Fuel ATR Flux Trap Top Head Penetration ATR Vessel AGC Connections to Control Systems 15

16 Michael DavenportIdaho National Laboratory 526-6214 16

Download ppt " 3 rd Advanced Graphite Creep Capsule (AGC-3) Irradiation Proceedings of the 2013 14 th International Nuclear Graphite Specialists Meeting INGSM-14."

Similar presentations

Ads by Google