Wir schaffen Wissen heute für morgen

Similar documents
Current Status of Pulsed Spallation Neutron Source of J PARC

ESS Target Facility Design. John Haines for the ESS Target Project Team

The Status of Studies on Structural Materials under High Energy Proton and Neutron Mixed Spectrum

MEGAPIE experiment. EURISOL 2nd TOWN MEETING. January 24th and 25th, 2002 ITALY. Th. Kirchner

School on Pulsed Neutrons: Characterization of Materials October Spallation Target Technology

David A. McClintock Maxim N. Gussev

LOS ALAMOS AQUEOUS TARGET/BLANKET SYSTEM DESIGN FOR THE ACCELERATOR TRANSMUTATION OF WASTE CONCEPT

MATERIAL RESPONSE TO HIGH POWER BEAMS. Goran Škoro ISIS, STFC, UK

Current Status of the High Intensity Pulsed Spallation Neutron Source at J-PARC )

OVERVIEW OF THE NSNS TARGET STATION* To be presented at the American Nuclear Society 1997 Annual Meeting Orlando, Florida June 1-5, 1997

Material Development for Spallation Target at JAERI

European Spallation Source ERIC Target Helium Cooling

MYRRHA FUEL TRANSIENT TESTS PROJECT AT THE TRIGA-ACPR REACTOR

TARGET OPERATION AT THE HIGH-POWER NEUTRON SPALLATION SOURCE SINQ SAFETY AND RELIABILITY ISSUES

Status Update 18MW ILC Beam Dump Design

Research and Development Activities for Accelerator Driven System at JAERI

Mechanic properties and microstructure of CLAM steel irradiated in STIP-V

Neutronic Challenges in SCWR Core Design. T. K. Kim Argonne National Laboratory

Conceptual Designs for a Spallation Neutron Target Constructed of a Helium-Cooled, Packed Bed of Tungsten Particles

Combining diffraction and imaging for the study of structural phase transitions

The new material irradiation infrastructure at the BR2 reactor. Copyright 2017 SCK CEN

Use of SERPENT at PSI/EPFL for thermal system analysis.

Tools and applications for core design and shielding in fast reactors

Neutron applications laboratory for ESS-BILBAO

Present Status and Future Potential for Commercial Application of JAEA Research Reactors. Masahiro ISHIHARA

BLIP 2017 Summary and 2018 Plans

Design Windows and Roadmaps for Laser Fusion Reactors

Task III presentations

Application of COMSOL Pipe Flow Module to Develop a High Flux Isotope Reactor System Loop Model

Systems for Neutrino Facilities. STFC Rutherford Appleton Laboratory

Unprotected Transient Analyses of Natural Circulation LBE-Cooled Accelerator. Driven Sub-critical System. Abstract:

Microstructural changes in ferritic-martensitic steels under mixed proton-neutron irradiation

Department Hotlabor. Didier Gavillet :: Department Hot Laboratory :: Paul Scherrer Institut. NES Event,

Accelerator targets design - The challenge of high power density. Ido Silverman DAPNIA visit 24/10/07

Table S-2. Roadmapping Neutron Sources. Table S-2. Roadmapping Neutron Sources (continued)

Conceptual Design, Neutronic and Radioprotection Study of a Fast Neutron Irradiation Station at SINQ

Supercritical Water Reactor Review Meeting. Materials Issues

18th International Symposium on Zirconium in the Nuclear Industry

Maintenance Concept for Modular Blankets in Compact Stellarator Power Plants

Los Alamos Transmutation Research

LNM: Labor für Nukleare Materialien

High Power Protons: ESS & ADS. Steve Peggs, ESS & BNL

Module 06 Boiling Water Reactors (BWR)

Module 06 Boiling Water Reactors (BWR)

Water Erosion Experiment Update. T.Davenne O.Caretta S.Bennetton 5 th Dec 2013

Cyclic Stress-Strain Curve for Low Cycle Fatigue Design and Development of Small Specimen Technology

KIPT ADS Facility. Yousry Gohar 1, Igor Bolshinsky 2, Ivan Karnaukhov 3. Argonne National Laboratory, USA 2. Idaho National Laboratory, USA 3

Shielding Calculation for the Target Station Design

Irradiation Testing of Structural Materials in Fast Breeder Test Reactor

Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup

Feasibility Study on the Fast-Ignition Laser Fusion Reactor With a Dry Wall FALCON-D*

(SAD): coupling all major components of an accelerator driven system (ADS) for nuclear waste incineration

4.3 SAFETY RESEARCH PROGRAM OF LWR FUELS AND MATERIALS USING THE JAPAN MATERIALS TESTING REACTOR

Salford, 27 Nov Thorium. The Alternative Nuclear Fuel? Bob Cywinski School of Applied Sciences

ADVANCED OPTIONS FOR TRANSMUTATION STRATEGIES. M. Salvatores CEA-DRN Bât. 707 CE/Cadarache Saint-Paul-Lez-Durance Cedex France.

Decommissioning of Nuclear Facilities in Switzerland Lessons learned

A study of reactivity control by metallic hydrides for Accelerator Driven System

The MIT Research Reactor as a National User Facility for Advanced Materials and Fuel Research

Fritz Leibundgut :: Decommissioning Officer :: Paul Scherrer Institut

Conversion of MNSR (PARR-2) from HEU to LEU Fuel

Irradiation Facilities at the Advanced Test Reactor International Topical Meeting on Research Reactor Fuel Management Lyon, France

Module 06 Boiling Water Reactors (BWR) Vienna University of Technology /Austria Atominstitute Stadionallee 2, 1020 Vienna, Austria

Concept Design and Thermal-hydraulic Analysis for Helium-cooled ADS

VVER-440/213 - The reactor core

Experimental Facilities and Plan for a Prototype SFR

OECD Transient Benchmarks: Preliminary Tinte Results TINTE Preliminary Results

Windowless target Electron Beam Experimental Irradiation

Activities for Safety Assessment of Fast Spectrum Systems

Status of Compatibility Facilities and Experiments on LBE with CLEAR-I Structural Materials

Burn up Analysis for Fuel Assembly Unit in a Pressurized Heavy Water CANDU Reactor

A. Kaliatka, S. Rimkevicius, E. Uspuras Lithuanian Energy Institute (LEI) Safety Assessment of Shutdown Reactors at the Ignalina NPP

Experimental Potentialities of the MBIR Reactor

Transmutation Products in Steel and Tungsten Samples at FMITS

Status Report and Documentation of DCLL Design

Preliminary design for a China ITER test blanket module

STRENGTH OF STEELS EXPOSED TO HEAVY LIQUID METALS

NuMI/LBNF Radiation Protection. Jim Hylen NBI September 2017

4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO

Physics Design of 600 MWth HTR & 5 MWth Nuclear Power Pack. Brahmananda Chakraborty Bhabha Atomic Research Centre, India

The GUINEVERE-project at VENUS

Wir schaffen Wissen heute für morgen

Design of Solid Breeder Test Blanket Modules in JAERI

TRANSMUTATION OF DUPIC SPENT FUEL IN THE HYPER SYSTEM

High performance blanket for ARIES-AT power plant

IFE Reactor Chamber Design and Blanket Issues Some Comments

Physical Properties. Can increase the strength by cold working but the recrystallization temperature is 400 to 500 C

JAEA's R&D Activities on Transmutation Technology for Long-lived Nuclear Wastes

Trends in Transmutation Performance and Safety Parameters Versus TRU Conversion Ratio of Sodium-Cooled Fast Reactors

Summary of Major Features of ARIES- ST and ARIES-AT Blanket Designs

Energy efficiency and saving potential analysis of the high intensity proton accelerator HIPA at PSI

In-core measurements of fuel-clad interactions in the Halden reactor

EXPERIMENTS WITH PREIRRADIATED FUEL RODS IN THE NUCLEAR SAFETY RESEARCH REACTOR. O.Horiki.S.Kobayashi,I.Takariko and K.Ishijima

nuclear science and technology

Sustainable Thorium Energy for the World

A Comparison of the PARET/ANL and RELAP5/MOD3 Codes for the Analysis of IAEA Benchmark Transients

Fast Reactor Operating Experience in the U.S.

ARIES-AT BLANKET AND DIVERTOR

IAEA Technical Meeting on Priorities in Modelling and Simulation for Fast Neutron Systems

MEGAPIE Target : DESIGN IMPLEMENTATION AND PRELIMINARY TESTS OF THE FIRST PROTYPICAL SPALLATION TARGET FOR FUTURE ADS

Production of High Power and Large-Area Negative Ion Beams for ITER

Transcription:

Paul Scherrer Institut Wir schaffen Wissen heute für morgen Spallation Target Developments B. Riemer (ORNL), H. Takada (JAEA), N. Takashi (JAEA) and M. Wohlmuther (PSI) Thorium Energy Conference 2013 (ThEC13), 27. 31. October 2013, CERN, Switzerland

Spallation Neutron Sources IPNS & KENS (not seen on the slide; I av =6 μa @ 500 MeV) have been decommissioned. New sources built in China (CSNS) and planned in Lund, Sweden (ESS). Thorium Energy Conference 2013 (ThEC13), 27 31 October 2013, CERN, Switzerland

Spallation Neutron Sources Facility Status / rep. rate Energy Target Type / Time structure Coolant Power Level [kw] Additional Information IPNS (ANL) decom. 30 Hz 0.450 Solid SP H 2 O 7 Depl. U / W ISIS TS 1 (RAL) running 50 Hz 0.800 Solid SP H 2 O 100-200 Depl. U / Ta / W-Ta clad ISIS TS 2 (RAL) running 10 Hz 0.800 Solid SP H 2 O 48 W-Ta clad Lujan Center (LANL) running 20 Hz 0.800 Solid SP H 2 O 100 W KENS (KEK) decom. 20 Hz 0.500 Solid SP H 2 O 3 W-Ta clad SINQ (PSI) running 51 MHz 0.575 solid/liquid CW D 2 O/LBE 800 1000 Zr / Pb-SS clad / Pb-Zr clad / LBE SNS (ORNL) running 60 Hz 1.000 Liquid SP Hg 1000 1.4 MW design JSNS (J-PARC) running 25 Hz 3.000 Liquid SP Hg 1000 1.0 MW design Thorium Energy Conference 2013 (ThEC13), 27 31 October 2013, CERN, Switzerland

SINQ @ PSI Target bulk shielding Proton beam on SINQ: 575 MeV / 51 MHz p-current: 1.5 / 1.6 ma Power: 0.8-0.9 MW

1997-1999: Target Mark I Water-cooled Zircaloy rods Target Evolution at SINQ 2000-2003:Target Mark II: Lead rods, steel clad 42% increase in neutron yield 2004 2008:Target Mark III hybrid Pb SS & Pb Zr-clad 2009 present: Target Mark IV Lead rods, with Zr clad, blanket Aug - Dec 2006: MEGAwatt Pilot Experiment: Joint international initiative to design, build, licence, operate and explore a liquid metal spallation target for 1 MW beam power (Details next talk)

Basic Design - MARK IV Target Basic parameters main loop Proton current: 1.5 1.6 ma Double Gaussian Beam Profile σ x =2.14 cm, σ y =2.96cm Peak Current Density: 25 µa/cm 2 /ma* D 2 O Cooling: p stat =8 bar Peak power deposition: 512 W/cm 3 /ma D 2 O inlet temp: 30ºC D 2 O outlet temp: 70ºC * no immediate damage at 70 µa/cm 2 Total Power Deposition in Target Assembly ~ 575 610 kw Materials Low neutron absorption cross sections (continuous, reactor-like source) Cladding material: Zircaloy II Main Target material: Pb (Sb-free) Blanket material: pure Al Safety Shroud: AlMg3 Coolant: D 2 O

Up to now the targets have performed as predicted. Currently investigations of on-line health monitoring system using TCs, vibration and acceleration sensors. SINQ MARK IV Target

MEGAPIE Neutronic Simulations MARK III Target 7 MARK IV Target 8 Simulated flux maps (MCNPX) of MEGAPIE, Target 7 (MARK III) and a MARK IV target Simulated differences to Target 6 are: MEGAPIE (~1.80), Target 7 (1.20*), Target 8 (~ 1.60). *if STIP samples are included (1.10)

Lifetime, Damage & PIE Lifetime limiting component of SINQ target: AlMg3 safety shroud Period of usage: limited to 2 years Operation cycle (accumulated charge > 13 Ah): Beam on Target ~ April/May Dec. Damage: Embrittlement Fatigue (due to interrupts / UCN) Failure of Cannellonis seldomn Cannelloni Failure (T6) AlMg3 BEW SINQ Target Irradiation Program (STIP) dpa rate in Zr-cladding Miniaturized samples inserted into SINQ target(s) Position dependent damage rates Investigation after storage time (~ 2 years) & unpacking (complete remote handling) Thorium Energy Conference 2013 (ThEC13), 27 31 October 2013, CERN, Switzerland

Operation Data of SINQ

Core of SNS target monolith Target Liquid H 2 moderators Inner Reflector Plug Outer Reflector Plug Proton Beam Window Core Vessel Core Vessel Inserts Shutters Water moderator

SNS Mercury Target Module 316L Mercury Target Vessel Target-to-Core Vessel Inflatable Seal 316L Water-cooled Shroud Proton Beam quasi-stagnation region at the center of the window Channel Hg flow V max : 2.4 ~ 3.5 m/s Bulk mercury flow has two supplies and one return

Mercury Loop Parameters @ 2 MW Power absorbed in Hg 1.2 MW Nom Op Pressure 0.3 MPa Flow Rate 340 kg/s V max (In Window) 3.5 m/s Temperature Inlet to target 60ºC Exit from target 90ºC Total Hg Inventory 1.4 m 3 Centrifugal Pump Power 30 kw Peak power density in mercury ~ 800 MW/m 3 @ 2 MW SNS Hg Target operates at low temperature and pressure Local pressure rise is 38 MPa (380 atm compared to static pressure of 3 atm!)* Mercury expansion and wave reflection at the vessel interface lead to tension in the mercury and cavitation

Pressure pulse effects on target vessel Includes an empirical model for cavitation in mercury Benchmarked with Hg target test data obtain at LANSCE WNR * Needed for estimating the fatigue life of the vessel Vessel dynamic stress see B.W. Riemer / J. of Nuclear Mater. 343 (2005) 81 91 Mercury pressure evolution * LANSCE WNR: Los Alamos Neutron Science Center Weapons Neutron Research

Two to five cuts have been made in Targets 1-7 Remotely operated annular cutter Targets have been inspected using: Through shield-window high-resolution photography Direct photography of disk specimens Internal examinations using security video cameras and articulating videoprobes PIE of SNS Targets Inner wall specimen from T1 ( =60 mm)

Cavitation-induced erosion on inner wall Left offset Center Right offset Target 4 Target 5 View from inside target looking into the beam

A Bubble Injection to Mitigate Cavitation Damage Close Collaboration between SNS & JSNS C B Bubbles <50 m A B Contraction 3 mechanisms for each region Center of thermal shock : A Absorption Propagation path : B Attenuation Negative pressure field : C Suppression C Thermal diffusion Thermal expansion Pressure wave Kinetic energy Thermal energy Absorption of the thermal expansion of mercury due to the contraction of micro bubbles Attenuation of the pressure waves due to the thermal dissipation of kinetic energy Suppression against cavitation bubble by compressive pressure emitted from gas-bubble expansion. Absorption Attenuation Suppression

Bubbling effect on vibration Laser Doppler Vibrometer measurements at J-PARC (MLF) Target 310kWeq. 2.8J/cm 3 /pulse No-bubbles Bubbles First peak is reduced; Same trends observed for the side wall vibration of the WNR experiment

Power on target & accumulated energy Major Remote Handling Component Replacements - Target - PBW - Shutter - CVI 1 2 3 4 5 6 7

Acknowledgement We would like to thank Ashraf Abdou, Michael Dayton, David McClintock and Mark Wendel from ORNL. Moreover our thanks go to Werner Wagner, Kurt Geissmann, Frank Heinrich and the whole team of the PSI target development group. Finally,.

Thank you for your attention.