Facility readiness evaluation for High-Z experiments at the NIF. (b)(6)
|
|
- Allison Rich
- 6 years ago
- Views:
Transcription
1 Facility readiness evaluation for High-Z experiments at the NIF (b)(6)
2 Facility Readiness Overview Evaluated the use of High Z materials from a Safety Basis / SWEIS and worker safety point of view Results indicate that it is feasible to deploy these targets but is dependent on: Mass and isotopics of the target material Target debris catcher efficiency Additional operational equipment Evaluated target transport, handling and recovery No significant facility modifications anticipated Procedural modifications will be necessary Evaluated designs and concepts for target debris catchers Catcher is necessary to reduce inventory, impact on long-term operational efficiency, and worker exposure potential 2
3 Facility Readiness Overview, Continued Details/impacts of some aspects have not yet been evaluated Diagnostics loop Optics loop Support services (e.g. bioassay program) It is essential that we start to maintain configuration managed point designs for each platform as we proceed with this project Directionality of ejecta was not evaluated, and this could further limit allowable target parameters or required catcher efficiency Experiments are needed to evaluate target ejecta/performance 3
4 NIF Hi-Z Target Experiments - Concept of Operations Hi-Z Targets fabricated outside of NIF and delivered individually prior to the shot Targets transported using standard LLNL Protocols Upon arrival at NIF, material entered into NIF s Inventory Mass/Isotopic make up provided by WCI Alpha contamination protocols fully implemented Target Loaded/catcher deployed 4
5 NIF Hi-Z Target Experiments - Concept of Operations (cont.) Experiment conducted Target, catcher and diagnostic assemblies retrieved using alpha protocols Target/Catcher assembly returned to WCI Requirement: WCI conducts assay to determine residual mass and its isotopics NIF is notified with residual mass analysis and NIF inventory updated 5
6 Operating Envelope for High-Z Materials Safety Basis Limits total amount of material in the Target Chamber at any given time Worker Safety Surface Contamination: limits isotopics and amount deposited per target Impact of High-Z material based on: 1) Containment and capture efficiency 2) Radionuclide mix 3) Mass of target 6
7 Limitations and Constraints - Safety Documentation Safety and Environmental Documentation SWEIS Limits the amount of material allowed in the Target Chamber Forms basis (source term) for public impact from catastrophic incident Does not allow use of WG without containment Safety Basis Falls within SWEIS Limited to 100 mg WGE total in the chamber Declares NIF as less than Category 3 (non-nuclear) facility Safety Basis Limits may be approached as material (dispersible or intact) accumulates within the Target Chamber 7
8 Limitations and Constraints Worker Safety Aspects Workplace type (glovebox, hood, etc) Positioners, etc. are Type 2 Work Place negative-air enclosures We expect to be well below the Type 3 Work Place (glovebox) threshold Continuous air monitoring system (CAMS) for alpha Currently not installed in the facility Portable instruments will be used Target throughput limited so that permanent CAMS not required Contamination Guideline for Entrant Components Levels to support campaign and hardware design identified Design driver Higher contamination levels within the Target Chamber are thought to be manageable 8
9 Limitations and Constraints Other aspects appear to be non-limiting Criticality Well below thresholds Accountable material control Well below thresholds Environmental monitoring Existing stack monitoring equipment is fully capable TRU waste Estimates indicate we will not produce TRU waste Managing contamination on Entrant Components is Limiting (hazard control) 9
10 Personnel Protection Alpha Contamination Management Handling positioners and associated components is routine therefore, we need to be confident that we can manage these levels on an ongoing basis Positioners not designed to act as glove boxes, but are negative air enclosures therefore, there are limits to contamination levels that can be safely managed in this environment Positioner max removable contamination criteria (Alpha) 2x10 4 dpm/100cm 2 Small, discrete item max removable contamination criteria (Alpha) 2x10 6 dpm/100cm 2 Directionality of ejecta could impact estimated contamination levels and will need further evaluation 10
11 Personnel Protection Contamination Management High-Z operations would add: Respirators Personal air samplers Components covered/bagged Routine decon/wipe down Alpha monitoring Provides real-time feedback on contamination levels Current contamination control practices 11
12 Personnel Protection Contamination Management Two gloveboxes are available in the Hazardous Materials Management Area Activation will take ~ $0.5M and approx 6 months Gloveboxes may be required for disassembly and/or decontamination of removed items 12
13 High Z Targets & Assumptions Potential Targets evaluated 8 mg, 4.5 mg 100% 242 mix 242 mix + 1% WGE 0.7 mg, 0.15 mg Assumptions 100% 242 mix 242 mix + 1% WGE 100 % WGE, Evaluated but not permissible under SWEIS Am-241 removed from 242 mix at time of fabrication Hi-Z materials will not be subjected to neutron yields Target Chamber will not be cleaned/de-inventoried, but entrant components are cleaned between shots Ablated material uniformly distributed 13
14 Allowable High-Z Materials Evaluation Results Ripple Target This plot assumes the full allocation (50% of the SB) is used for this target type 14
15 Allowable High-Z Materials Evaluation Results Stepped Target This plot assumes the full allocation (50% of the SB) is used for this target type 15
16 Allowable High-Z Materials Evaluation Results Flat Target This plot assumes the full allocation (50% of the SB) is used for this target type 16
17 Allowable High-Z Materials Evaluation Results All Targets Small Diffraction Large Diffraction RT and EOS For a combination of targets, the sum of the ratios of actual number of each target to its limit must be less than 1 17
18 Allowable High-Z Materials Evaluation Results large targets # of shots to reach limit (b)(5) Larger targets require high catcher efficiency 18
19 High-Z Materials Preparations and Start up NIF Follows Work Authorization Point (WAP) process to authorize work Identifies the set of items to be completed before authorization Facility Preparedness Equipment acquisition Procedure development/modification Personnel training Necessary additional resources: Alpha contamination monitors Portable continuous air monitors NIF Glove Box commissioning (if required) Management Prestart Review (MPR) Independent review of readiness Other Impacts need further evaluation Optics (Purged storage and B391 OPF/OMF), Diagnostics, lab support 19
20 Catcher high level requirements and assumptions Catcher minimizes NIF inventory and worker exposure potential Resources need to be allocated to design catcher Material to be returned to WCI; material specification / format not yet defined Capture efficiency requirements TBD; detailed requirements not defined May vary by target type and target assay Amount captured must be quantified to allow removal from inventory Accuracy may depend upon efficiency achieved and margin to limits Larger mass targets require an effective catcher 20
21 Catcher high level requirements and assumptions Catcher must survive anticipated debris, 1w, and x-ray load for energy ranges of interest for campaigns Assume deployed on existing NIF positioners; may require new payloads/end effectors Target must fit in TAS for alignment; adequate alignment DOF s must be available to align target, backlighters and catcher Catcher may or may not be co-located with target; may be distributed to meet requirements Must meet NIF TC operational criteria: material compatibility, handling limitations, shot cycle interfaces, align-ability and stability 21
22 Catcher design status and issues Strength/EOS campaign catcher design status: There currently is NO mature concept for a catcher that meets fundamental requirements Both survivability and capture efficiencies are issues Significant modeling is required to predict material dispersion and distribution Interplay between target, required diagnostics and catcher is complicated Timely recovery of diagnostic data may determine where post-shot activities occur Diffraction campaign catcher design status: The lower energy and target mass of TARDIS design improves likelihood that catcher requirements could be met for this campaign TARDIS experiments in CY13 will provide some relevant information Significant modifications of the base design are required for planned campaigns Catcher design would benefit from use of surrogate material during testing (see next slide) Limited 1 st principle concept testing is starting on Omega in May Initial use of small targets facilitates phased catcher development 22
23 Catcher testing and validation To validate performance of a catcher, test shots with a TBD surrogate material may be required Captured material measurement techniques may include: Mass measurement Activity measurement Chemical separation with one of the above Others? Surrogate material must: Have similar melt/vaporization response to planned target material Be differentiable from other NIF target/tc materials Be consistent with chosen measurement techniques (e.g., may need to be radioactive to test radio-assay technique) Surrogate development must be pursued in concert with catcher design 23
24 Preliminary proposed catcher development schedule Catcher development needs to be organized as a full project 24
25 Diagnostics have been identified for High Z experiments Diagnostic Experimental platform Issues (b)(3) SuperSnout II (0, 0) Diffraction, Strength (b)(3) Potentially contaminated image plates and hardware Dante I (143, 274) Diffraction, EOS, Strength Connected to TCV (b)(3) (b)(3) SXI U/L Diffraction, EOS, Strength (b)(3) Requires new snout configuration for diffraction Potentially contaminated hardware (b)(3) (b)(3) FABs EOS, Strength None, No contact with TCV NBI EOS, Strength None, No contact with TCV FFLEX Strength (EOS optional) None, No contact with TCV EHXI Strength (EOS optional) None, No contact with TCV
26 Diagnostics design and interfaces No new diagnostic designs are required Diagnostic to catcher interface could require engineering design TARDIS could be integrated Others are more difficult Post shot diagnostic handling protocols need to be developed DIM diagnostics (HEIDI, GXD, VISAR) SXI s Dante Protocol would follow Be handling protocol as an example Decontamination of data media will need consideration Setup contaminated Image plate reader Decontaminate Image plate and read clean Contamination levels will determine process
27 Process diagram for target diagnostic components Shot RI selects diagnostics in CMT Diagnostic assembly in standard NIF factory Diagnostic LRU s loaded into respective locations NIF shot generating WPE Connected to TCV Yes No Process as normal Follow contamination protocol Survey diagnostic components Alpha contamination on Parts? Yes No Process as normal Recover data media in glove box Decon media Decon parts or Dispose Process as normal
28 Action Items - Engineering Engineered controls preferred over PPE/Admin controls e.g. Local enclosures Consider redesign of entrant components (e.g. snout) to ease decon Specification of Capture efficiency should be avoided Develop FMEA Evaluate oxide forms Evaluate effects of Hi-Z materials on image plate 28
29 Action Items - Administrative Evaluate operational impact on non Hi-Z shots Define protocols for non Hi-Z shots Evaluate human factors (worker proficiency, training, skills, etc.) Clarify material limits based on state (solid, liquid, vapor) 29
30 Action Items - Communication Develop communication strategy (b)(5) 30
31 Facility Readiness Overview Evaluated the use of High Z materials from a Safety Basis / SWEIS and worker safety point of view Results indicate that it is feasible to deploy these targets but is dependent on: Mass and isotopics of the target material Target debris catcher efficiency Additional operational equipment Evaluated target transport, handling and recovery No significant facility modifications anticipated Procedural modifications will be necessary Evaluated designs and concepts for target debris catchers Catcher is necessary to reduce inventory, impact on long-term operational efficiency, and worker exposure 31
32 Facility Readiness Overview, Continued Details/impacts of some aspects have not yet been evaluated Diagnostics loop Optics loop Support services (e.g. bioassay program) It is essential that we start to maintain configuration managed point designs for each platform as we proceed with this project Directionality of ejecta was not evaluated, and this could further limit allowable target parameters or required catcher efficiency Experiments are needed to evaluate target ejecta/performance 32
33 33
Health Physics Support for High Specific Activity TRU Waste Processing Project
Health Physics Support for High Specific Activity TRU Waste Processing Project Presented by Martin Brennan At AMUG Technical Meeting April, 2012 Sandia is a multiprogram laboratory operated by Sandia Corporation,
More informationIAEA SAFETY STANDARDS for protecting people and the environment. Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities
DS447 Date: 20 February 2015 IAEA SAFETY STANDARDS for protecting people and the environment STATUS: SPESS STEP 12 For submission to CSS Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle
More informationCMMI FOR SERVICES, THE PREFERRED CONSTELLATION WITHIN THE SOFTWARE TESTING FUNCTION OF A SOFTWARE ENGINEERING ORGANIZATION
CMMI FOR SERVICES, THE PREFERRED CONSTELLATION WITHIN THE SOFTWARE TESTING FUNCTION OF A SOFTWARE ENGINEERING ORGANIZATION NAME: Nestor K. Ovalle, PhD TITLE: Leadership & Corporate Change Consultant; CMMI
More informationINEEL REMOTE-HANDLED TRANSURANIC WASTE INVENTORY, WASTE DISPOSITION PLANS, AND TECHNOLOGY NEEDS
INEEL REMOTE-HANDLED TRANSURANIC WASTE INVENTORY, WASTE DISPOSITION PLANS, AND TECHNOLOGY NEEDS Thomas L. Clements, Jr., Craig R. Tyler, and Michael E. McIlwain Bechtel BWXT Idaho, L.L.C. ABSTRACT Idaho
More informationDECOMMISSIONING STRATEGIES AND PLANS. By: Elna Fourie Necsa South Africa Manager: Decommissioning Services
DECOMMISSIONING STRATEGIES AND PLANS By: Elna Fourie Necsa South Africa Manager: Decommissioning Services 2011 SELECTION OF A DECOMMISSIONING STRATEGY The two most common decommissioning strategies are
More informationRequirements for Pu NIF targets
Requirements for Pu NIF targets June 2011 OFFICIAL USE ONLY May be exempt from public release under the Freedom of Information Act (5 U.S.C. 552), Exemption number and category: Exemption 5, Privileged
More informationSTATEMENT OF WORK SMALL SPACECRAFT PROTOTYPING ENGINEERING DEVELOPMENT & INTEGRATION (SSPEDI) Space Solutions (SpS)
SSPEDI SpS J.1(a), Attachment 1 80ARC018R0007 National Aeronautics and Space Administration Ames Research Center Moffett Field, CA 94035-0001 STATEMENT OF WORK SMALL SPACECRAFT PROTOTYPING ENGINEERING
More informationWM2015 Conference, March 15 19, 2015, Phoenix, Arizona, USA
Design and Testing of a Sensitive Heat-Flow Calorimeter for Measuring Radioactive Waste in 55-Gallon (US) Drums -15334 John A. Mason*, Charles Bonner**, Kevin J. Burke*, Lynn Foster**, Lawrence V. Odell*,
More informationNATIONAL PROGRESS REPORT INDONESIA
NATIONAL PROGRESS REPORT INDONESIA 2015-06-30 0. INTRODUCTION The Research Reactor Decommissioning Demonstration Project (R2D2P) was developed to provide a platform for training and exchange of information,
More informationEnvironmental ALARA Program Plan
Environmental ALARA Program Plan Prepared by Environment, Health and Safety Division Environmental Services Group March 8, 2013 Revision 6 PP5001 Ernest Orlando Lawrence Berkeley National Laboratory Berkeley,
More informationManufacturing Nuclear Weapon Pits : Paths toward 80 Pits Per Year
Manufacturing Nuclear Weapon Pits : Paths toward 80 Pits Per Year Presentation to Nuclear Deterrence Summit Jonathan Medalia Congressional Research Service February 19, 2015 1 Pit Fissile core of a nuclear
More informationWM2012 Conference, February 26 March 1, 2012, Phoenix, Arizona, USA. Treatability Variance for Containerized Liquids in Mixed Debris Waste 12101
Treatability Variance for Containerized Liquids in Mixed Debris Waste 12101 Catherine M. Alstatt Transuranic Waste Processing Center, Lenoir City, TN 37771 Wastren Advantage Inc. ABSTRACT The TRU Waste
More informationVALIDATION AND PERFORMANCE TEST OF THE PLUTONIUM INVENTORY MEASUREMENT SYSTEM (PIMS) AT THE ROKKASHO REPROCESSING PLANT (RRP)
VALIDATION AND PERFORMANCE TEST OF THE PLUTONIUM INVENTORY MEASUREMENT SYSTEM (PIMS) AT THE ROKKASHO REPROCESSING PLANT (RRP) ABSTRACT Dan Parvin British Nuclear Group, Project Services Limited, UK At
More informationSoftware Customization Services. Measurement solutions for nuclear safety and security.
Software Customization Services Measurement solutions for nuclear safety and security. CANBERRA Services 1-800-225-6370 Software Customization Services Our Software Customization Services are designed
More informationIAEA SAFETY STANDARDS for protecting people and the environment. Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities
DS447 Date: September 2014 IAEA SAFETY STANDARDS for protecting people and the environment STATUS: SPESS STEP 11 MS comments incorporated Review Committee Member comments due 31 Oct Predisposal Management
More informationJames D. Kopotic United States Department of Energy Oak Ridge Office P.O. Box 2001 Oak Ridge, TN
Lessons-Learned from D&D Activities at the Five Gaseous Diffusion Buildings (K-25, K- 27, K-29, K-31 and K-33) East Tennessee Technology Park, Oak Ridge, TN 13574 James D. Kopotic United States Department
More informationNeutron Activation of the NIF Final Optics Assemblies and Their Effect Upon Occupational Doses
UCRL-JC-129515 PREPRINT Neutron Activation of the NIF Final Optics Assemblies and Their Effect Upon Occupational Doses J. F. Latkowski This paper was prepared for submittal to the 1998 American Nuclear
More informationMathematical Modelling of Regional Fuel Cycle Centres
Mathematical Modelling of Regional Fuel Cycle Centres by Leonard L. Bennett and Larry D. Reynolds The concept of Regional Fuel Cycle Centres (RFCC) has attracted wide interest as a possible approach towards
More informationAdvanced Non-Destructive Assay Systems and Special Instrumentation Requirements for Spent Nuclear Fuel Recycling Facilities
Advanced Non-Destructive Assay Systems and Special Instrumentation Requirements for Spent Nuclear Fuel Recycling Facilities - 8032 ABSTRACT A. P. Simpson, M. J. Clapham, B. Swinson Pajarito Scientific
More informationEngineering Support and Qualification Process for Interfacing New Experiments
Engineering Support and Qualification Process for Interfacing New Experiments G. Pien University of Rochester Laboratory for Laser Energetics Omega Laser Facility Users Group Workshop Rochester, NY 29
More informationADVANCED DECONTAMINATION AND DECOMMISSIONING SYSTEM
ABSTRACT ADVANCED DECONTAMINATION AND DECOMMISSIONING SYSTEM Julia L. Tripp Idaho National Engineering and Environmental Laboratory P.O. Box 1625 Idaho Falls, Idaho 83415-3720 Radioactive waste packaging
More informationExhibit A - Scope of Services AMI Implementation Project Management Services
Exhibit A - Scope of Services AMI Implementation Project Management Services Deliver to: City of Santa Rosa 90 Santa Rosa Avenue Santa Rosa, CA 95401 Attn: Kimberly Zunino City of Santa Rosa June 2, 2016
More informationWaste Isolation Pilot Plant
Waste Isolation Pilot Plant Advantic Leads Design and Delivery of Emergency Response Composite Structure Challenge On February 14, 2014 a 55-gallon drum of contaminated material burst at the U.S. Department
More informationRADIATION PROCEDURES MANUAL Procedure Cover Sheet
RADIATION PROCEDURES MANUAL Procedure Cover Sheet Procedure Title: Receipt of Package Containing Radioactive Material Procedure Number: TSO-10-18-REV 1 Effective Date: April 23, 2011 Date: April 23, 2011
More informationStatus of the National Ignition Facility s Control and Information Systems
Status of the National Ignition Facility s Control and Information Systems Presentation to 14 th International Conference on Accelerator & Large Experimental Physics Control Systems (ICALEPCS) October
More informationROCKY FLATS CENTRALIZED SIZE REDUCTION FACILITY PROJECT UPDATE
ROCKY FLATS CENTRALIZED SIZE REDUCTION FACILITY PROJECT UPDATE Brian Mathis Ronald Warnecke Robbin Duncan Kaiser Hill TRUTech, L.L.C. Polestar Applied Technology Rocky Flats Environmental P.O. Box 1365
More informationDRAFT IMPLEMENTING DECREE. of 2016
1. ------IND- 2016 0202 CZ- EN- ------ 20160523 --- --- PROJET II. DRAFT IMPLEMENTING DECREE of 2016 on the requirements for the safe management of radioactive waste and on the decommissioning of nuclear
More informationWM 2010 Conference, March 7-11, 2010 Phoenix, AZ
Optimized Planning of the Disposal of radioactive Waste Packages exceeding the German Waste Acceptance Criteria Limits for Fissile Material Content and for Heat Generation - 10450 Peter Brennecke, Stefan
More informationRadiation Safety Training Session 2: Radiation Protection Systems and Guidelines
Radiation Safety Training Session 2: Radiation Protection Systems and Guidelines Reading Assignment: LLEINST 6610 Part II, pp. 1 9 Walter T. Shmayda Radiation Safety Officer Laboratory for Laser Energetics
More informationNext Generation Lighting Systems Page 1 of INDOOR Competition Two Entrant Guide
2017 INDOOR Competition Two Easily Installed and Configured LED Troffer Conversion (Retrofit) Kits with Luminaire Integrated Sensors and Controls Entrant Guide Next Generation Lighting Systems Page 1 of
More informationTechnical Reports Safety Report - Public Summary
Technical Reports Safety Report - Public Summary Cameco Fuel Manufacturing Safety Analysis Report C ameco Corporation s (Cameco) Cameco Fuel Manufacturing (CFM) facility holds an operating licence from
More informationBenefits from R&D for D&D Projects Preparation
Benefits from R&D for D&D Projects Preparation Christine GEORGES 17th February 2016 Titre du document ~ February 2016 ~ 1 SPECIAL FEATURES OF CEA D&D PROJECTS 500 M /year 800 CEA employees and about 2500
More informationRISK ENGINEERING GUIDELINE
RISK ENGINEERING GUIDELINE BUSINESS CONTINUITY MANAGEMENT (BCM) HDI Risk Consulting Business Interruption www.hdi.global Development and Implementation of a Business Continuity Management System (BCMS)
More informationC. Kennes - C. Mommaert - M. Van haesendonck (Bel V) H. Libon - A. De Backer (Belgonucleaire) Decommissioning of Belgonucleaire MOX plant
C. Kennes - C. Mommaert - M. Van haesendonck (Bel V) H. Libon - A. De Backer (Belgonucleaire) Decommissioning of Belgonucleaire MOX plant Content Regulatory framework Strategy Status of the project Role
More informationSymposium on Recycling of metals, April 8-10, 2014, Studsvik. The Metal Recycling Process and its Nuclide Distribution
Symposium on Recycling of metals, April 8-1, 214, Studsvik The Metal Recycling Process and its Nuclide Distribution Per Lidar*, Maria Lindberg*, Arne Larsson*, and Patrik Konneus* * Studsvik Nuclear AB
More informationApplied CMMI-SVC: Identifying Service Systems and Improving Service System Capability
Applied CMMI-SVC: Identifying Service Systems and Improving Service System Capability SSTC Conference May 2011 Dr. Richard Bechtold : Importance of Service Systems A significant majority of the world s
More informationAccess. Access Laboratory Workstation BROCHURE READY-TO-GO ROBOTIC SYSTEMS FOR ECHO LIQUID HANDLERS. Version 2.1 MAY 2017 LABCYTE INC.
Access Laboratory Workstation READY-TO-GO ROBOTIC SYSTEMS FOR ECHO LIQUID HANDLERS Access BROCHURE Version 2.1 MAY 2017 LABCYTE INC. 170 Rose Orchard Way San Jose, CA 95134 USA Toll-free: +1 877 742 6548
More informationRegulatory Perspectives on Decommissioning of TEPCO Fukushima Daiichi Nuclear Power Station
Regulatory Perspectives on Decommissioning of TEPCO Fukushima Daiichi Nuclear Power Station July 3, 2017 Hiroshi YAMAGATA Nuclear Regulation Authority (NRA), Japan 1 Contents Contaminated water Radioactive
More informationIFE TARGET FABRICATION AND INJECTION
IFE TARGET FABRICATION AND INJECTION 1951 µm 1690 µm 1500 µm 0.8 µm of CH + 5% Au CH (DT) 64 Fuel DT Vapor Fast Gas Valve Gas Reservoir Target Loader Gun Barrel Transport from Target Factory Rotating Shield
More informationCMMI-SVC V1.3 CMMI for Services Version 1.3 Quick Reference Guide
processlabs CMMI-SVC V1.3 CMMI for Services Version 1.3 Quick Reference Guide CMMI-SVC V1.3 Process Areas Alphabetically by Process Area Acronym processlabs CAM - Capacity and Availability Management...
More informationUniversity of Maryland Baltimore. Radiation Safety Procedure
University of Maryland Baltimore Procedure Number: 2.1 Radiation Safety Procedure Title: Ordering, Receiving, Opening, And Transferring Packages Containing Revision Number: 0 Technical Review and Approval:
More informationNUCLEAR SAFETY REQUIREMENTS BSR
NUCLEAR SAFETY REQUIREMENTS BSR-1.8.2-2015 APPROVED BY Order No. 22.3-99 of The Head of State Nuclear Power Safety Inspectorate, of 7 October 2011 (as amended by Order No. 22.3-57 of the Head of State
More informationSafe Operating Procedure
Safe Operating Procedure (Reviewed 8/14) CONTAMINATION SURVEYS FOR RADIOACTIVE MATERIAL LABORATORIES The purpose of this document is to provide guidance for the performance of contamination surveys in
More informationMETHODS FOR MOUNTING RADIOACTIVE POWDERS FOR XRD ANALYSIS
54 METHODS FOR MOUNTING RADIOACTIVE POWDERS FOR XRD ANALYSIS Leah N. Squires, Robert D. Mariani, Thomas Hartmann* and J. Rory Kennedy Idaho National Laboratory, Fuel Fabrication and Characterization Department,
More informationCMMI V2.0 MODEL AT-A-GLANCE. Including the following views: Development Services Supplier Management. CMMI V2.0 outline BOOKLET FOR print.
CMMI V.0 MODEL AT-A-GLANCE Including the following views: Development Services Supplier Management CMMI V.0 outline BOOKLET FOR print.indd CMMI V.0 An Integrated Product Suite Designed to meet the challenges
More informationStatus and Update of the National Ignition Facility Radiation Effects Testing Program
UCRL-JC-131817 PREPRINT Status and Update of the National Ignition Facility Radiation Effects Testing Program C. R. Wuest J. F. Davis F. J. D. Serduke This paper was prepared for submittal to the 1999
More informationIMPROVED TECHNOLOGIES FOR DECONTAMINATION OF CRATED LARGE METAL OBJECTS
IMPROVED TECHNOLOGIES FOR DECONTAMINATION OF CRATED LARGE METAL OBJECTS (Los Alamos Release No: LAUR 03-0190) John McFee, Kevin Barbour Shaw Environmental Ellen Stallings Los Alamos National Laboratory
More informationIndependent Assessment of the Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) Repository in New Mexico, USA
Independent Assessment of the Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) Repository in New Mexico, USA June 6-9, 2016 APHL Seminar on Hot Topics in Radioanalytical Response -
More informationThe National Ignition Facility (NIF) Software Engineering Efforts Presentation to SIR Computers and Technology Group March 17, 2016
The National Ignition Facility (NIF) Software Engineering Efforts Presentation to SIR Computers and Technology Group March 17, 2016 Eric Stout NIF Controls Software Architect The NIF mission is to study
More informationFACILITY WASTE CHARACTERIZATION FOR D&D HEU, MIXED AND LLRW FOR CERCLA, RCRA, DOE AND NRC COMPLIANCE
FACILITY WASTE CHARACTERIZATION FOR D&D HEU, MIXED AND LLRW FOR CERCLA, RCRA, DOE AND NRC COMPLIANCE Frederick Gardner, CHP, DRS Gene Perry, PE, DRS Scott LaBuy, Project Manager, DRS Lance Escue, General
More informationRADIATION SAFETY INSPECTION CHECKLIST Section A : Contact Information (Principle Investigator) Last Name: First Name: Extension:
RADIATION SAFETY INSPECTION CHECKLIST Section A : Contact Information (Principle Investigator) Last Name: First Name: Extension: Department: Building: Room: Section B: Inspection Date of Inspection: Time
More informationLLEINST 6706G 26 October 2015 LLE INSTRUCTION 6706G BERYLLIUM SAFETY PROCEDURES
LLE INSTRUCTION 6706G SUBJECT: BERYLLIUM SAFETY PROCEDURES REFERENCES: a. 10 CFR Part 850 Chronic Beryllium Disease Prevention Program (CBDPP); Final Rule b. 29 CFR 1910.1450 (OSHA Laboratory Standard)
More informationGeorgia WIPPTREX 2015
Georgia Emergency Management Agency Homeland Security Georgia WIPPTREX 2015 Mark Wyland WIPP Coordinator June 25, 2015 What is WIPP? The U.S. Department of Energy s (DOE) Waste Isolation Pilot Plant (WIPP)
More informationOn the Practical Use of Lightbridge Thorium-based Fuels for Nuclear Power Generation
On the Practical Use of Lightbridge Thorium-based Fuels for Nuclear Power Generation Revision 1 - July 2010 Lightbridge Corporation 1600 Tysons Blvd. Suite 550 Mclean, VA 22102 USA P +1 571.730.1200 F
More informationB. Hartmann, M. Häger Energiewerke Nord GmbH P.O.Box 1125, Lubmin, Germany
Revk a Tool for the Fulfilment of Requirements from National Rules for Tracking and Documentation of Radioactive Residual Material and Radioactive Waste B. Hartmann, M. Häger Energiewerke Nord GmbH P.O.Box
More informationThis is Chapter 6, part-two of the Radiation Safety Short Course: Radioisotope Laboratory Techniques. In this section we will review what Radiation
This is Chapter 6, part-two of the Radiation Safety Short Course: Radioisotope Laboratory Techniques. In this section we will review what Radiation Safety personnel evaluate when completing the quarterly
More informationUsing Commercially Available Robotic Equipment to Sample and Remove Heels in Tanks with Internal Obstructions
Using Commercially Available Robotic Equipment to Sample and Remove Heels in Tanks with Internal Obstructions- 11239 Andrew J. Tisler Savannah River Remediation, LLC Aiken, SC 29808 SRR-LWE-2011-00010
More informationFSUE "MAYAK" PA ACTIVITIES IN THE FRAMEWORK OF RITEG DISPOSAL PROGRAM.
FEDERAL AGENCY FOR ATOMIC ENERGY FEDERAL STATE UNITARY ENTERPRISE "MAYAK PRODUCTION ASSOCIATION" FSUE "MAYAK" PA ACTIVITIES IN THE FRAMEWORK OF RITEG DISPOSAL PROGRAM. Yu.V. Glagolenko, A.A. Abramov, V.F.
More informationRadiological Services Radiation Protection Technician Development Program
Radiological Services Radiation Protection Technician Development Program Revision: Final Effective Date: 10-7-2017 Table of Contents 1.0 Introduction... 1 1.1 Purpose... 1 1.2 Scope and Applicability...
More informationDECONTAMINATION AND DECOMMISSIONING (D&D): A PROBLEM OF LARGE (BUT DEFINABLE) DIMENSIONS
DECONTAMINATION AND DECOMMISSIONING (D&D): A PROBLEM OF LARGE (BUT DEFINABLE) DIMENSIONS Ray Lawson, Blue Ridge Metrology, Inc. Gary A. Benda, U. S. Energy Corp. ABSTRACT The U. S. Department of Energy
More informationStatus of Fukushima Daiichi Decommissioning and Decontamination Project
E-Journal of Advanced Maintenance Vol.7-2 (2015) 154-159 Japan Society of Maintenology Status of Fukushima Daiichi Decommissioning and Decontamination Project Douglas M. Chapin 1,* 1 MPR Associates, 320
More informationRadioactive Waste Disposal
Workshop on safe handling of radioactive materials Radioactive Waste Disposal 26 July 2018 Mr Parthiban S/O Balachandran Technical Supervisor Radiation Protection & Nuclear Science Department Content i.
More informationLLNL Experiments at OMEGA in FY05
UCRL-TR-216229 LLNL Experiments at OMEGA in FY05 R. E. Turner October 17, 2005 Disclaimer This document was prepared as an account of work sponsored by an agency of the United States Government. Neither
More informationA MULTI-ATTRIBUTE UTILITY DECISION ANALYSIS FOR TREATMENT ALTERNATIVES FOR THE DOE-SR ALUMINUM-BASED SPENT NUCLEAR FUEL
A MULTI-ATTRIBUTE UTILITY DECISION ANALYSIS FOR TREATMENT ALTERNATIVES FOR THE DOE-SR ALUMINUM-BASED SPENT NUCLEAR FUEL Timothy Wheeler, Ruth Weiner, Freddie Davis, Ken Sorenson, Sandia National Laboratories
More informationThroughout the Development
Managing Acceptance Criteria Throughout the Development Lifecycle Shea Watrin, Cecilia Chin, Julie TerWee Amgen Quality Outline Acceptance criteria primer Criteria on day 1 What necessitates change? Is
More informationRenovating a Medical Radiosotope Production Hot Cell T. GROCHOWSKI ROBATEL Technologies
Renovating a Medical Radiosotope Production Hot Cell - 11337 T. GROCHOWSKI ROBATEL Technologies D. SANCHETTE & S. COLLONGE ROBATEL Industries Rue de Genève, 69740 Genas - France P. Van boxem National Institute
More informationCAPCOA Air Toxic Hot Spots Program
CAPCOA Air Toxic Hot Spots Program Facility Prioritization Guidelines Prepared by: California Air Pollution Control Officers Association (CAPCOA) Air Toxics and Risk Managers Committee (TARMAC) August
More informationUptime Maintenance and Support Services - Appendix. Dimension Data Australia Pty Limited. Uptime Support Services Agreement
Uptime Support Services Agreement Uptime Maintenance and Support Services - Appendix Dimension Data Australia Pty Limited 27 May 2013 Version 1-01 Appendix A. 1. Definitions and Interpretations 1.1 For
More informationNCHRP 8-92: Implementing Transportation Data Program Self- Assessment. NATMEC Working Together for Improved Travel Monitoring June 30, 2014
NCHRP 8-92: Implementing Transportation Data Program Self- Assessment NATMEC Working Together for Improved Travel Monitoring June 30, 2014 Agenda 1. Project Overview 2. Progress to Date Review of Methodology
More informationWestinghouse Waste Simulation and Optimization Software Tool 13493
Westinghouse Waste Simulation and Optimization Software Tool 13493 Kim Mennicken* and Dr. Jörg Aign** *Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstraße 44, D- 68167 Mannheim, Germany,
More informationWIPP Overview. Betsy Forinash. Director, National Transuranic Waste (TRU) Program-HQ Office of Environmental Management, DOE
WIPP Overview Betsy Forinash Director, National Transuranic Waste (TRU) Program-HQ Office of Environmental Management, DOE Presentation to the National Academy of Sciences November 28, 2017 www.energy.gov/em
More informationARC BRIEF. Using Simulation to Optimize Results of Automation Projects. Keywords. Summary. Applications of Simulation Systems.
ARC BRIEF AUGUST 30, 2006 Using Simulation to Optimize Results of Automation Projects By Tom Fiske Keywords Automation Checkout, MiMiC, Operator Training Simulator, Simulation Summary The use of simulation
More informationClosed-Loop Measurement of Equipment Efficiency and Equipment Capacity. Prof. Rob Leachman University of California at Berkeley
Closed-Loop Measurement of Equipment Efficiency and Equipment Capacity Prof. Rob Leachman University of California at Berkeley Introduction Important concept from "TPM" paradigm: Overall Equipment Efficiency
More informationicap 7000 Plus Series ICP-OES Streamlined performance and ultra-low ICP-OES detection limits for routine laboratories
icap 7000 Plus Series ICP-OES Streamlined performance and ultra-low ICP-OES detection limits for routine laboratories icap 7000 Plus Series ICP-OES Powerful multi-element performance for routine and research
More informationSan Onofre Unit 1 Decommissioning
San Onofre Unit 1 Decommissioning Eric M. Goldin, Ph.D., CHP Southern California Edison P. O. Box 128 San Clemente, CA 92674-0128 USA Introduction Nuclear plant decommissioning presents several challenges
More informationRADIOACTIVE WASTE MANAGEMENT PLAN
RADIOACTIVE WASTE MANAGEMENT PLAN Copies of this plan will be made available to all members of the campus community with the potential to generate radioactive waste. Contents I. Purpose II. Regulatory
More informationWM2015 Conference, March 15 19, 2015, Phoenix, Arizona, USA
Installation and Operation of GeoMelt In Container Vitrification in NNL Central Lab Active Rig Hall at Sellafield 15328 Keith Witwer *, Eric Dysland *, Steve Woosley *, Charlie Scales **, John McGibbon
More informationWASTE MANAGEMENT PROGRAM
Waste Management Program Page 1 of 23 WASTE MANAGEMENT PROGRAM 1.0 Objective The objective of this performance assessment is to evaluate the effectiveness of the laboratory's waste management program as
More informationHanford Low Activity Waste Historical Overview. David Swanberg February 2018
Hanford Low Activity Waste Historical Overview David Swanberg February 2018 1 Outline This session will cover: o Hanford Low Activity Waste (LAW) - origin and definition o Seminal decisions and factors
More informationDecommissioning of Nuclear Installations
Decommissioning of Nuclear Installations Definition of Decommissioning The administrative and technical actions taken to allow the removal of some or all of the regulatory controls from a nuclear facility
More informationRequirements Specification
Ambulance Dispatch System Submitted to: Dr. Chung Submitted by: Chris Rohleder, Jamie Smith, and Jeff Dix Date Submitted: February 14, 2006 TABLE OF CONTENTS 1.0 INTRODUCTION...1 1.1 PURPOSE...1 1.2 SCOPE...1
More informationMFC CH-TRU Waste Certification Plan
Document ID: Revision ID: 06//0 Plan MFC CH-TRU Waste Certification Plan The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance. 06//0 Page: ii of v Materials and
More informationPersonnel Contamination Monitoring NISP-RP-06
NUCLEAR INDUSTRY STANDARD PROCESS Radiological Protection NISP-RP-06 Effective Date: 5-10-2017 This is an industry document for standardizing radiation protection processes used by supplemental radiation
More informationDesign of Solid Breeder Test Blanket Modules in JAERI
Design of Solid Breeder Test Blanket Modules in JAERI Presented by: S. Suzuki, Blanket Engineering Lab., Japan Atomic Energy Research Institute, JAERI Contents 1. Outline of blanket development in JAERI
More informationRadioactive Material Transport Security. Ann-Margret Eriksson Eklund IAEA Office of Nuclear Security
Radioactive Material Transport Security Ann-Margret Eriksson Eklund IAEA Office of Nuclear Security Background Focus has been on Safety The rising threat of terrorism and sabotage is now recognized and
More informationBoiling Water Reactor Vessel and Internals Project (QA)
Boiling Water Reactor Vessel and Internals Project (QA) Program Description Program Overview As boiling water reactors have aged, various forms of operation-limiting stress corrosion cracking have appeared,
More informationFuture Challenges in Decommissioning of NPPs Worldwide
Future Challenges in Decommissioning of NPPs Worldwide Dr. Ivan Rehak, Dr. Michael Siemann Radiological Protection and Radioactive Waste Management OECD/NEA 1 Future in Decommissioning of Nuclear Power
More informationCapitalBio LuxScan TM. HT24 High Throughput Microarray Scanner. Exploit the full capacity of your lab
CapitalBio LuxScan TM HT24 High Throughput Microarray Scanner Exploit the full capacity of your lab Introduction CapitalBio LuxScan HT24 is our latest high throughput microarray scanner in the LuxScan
More informationThermo Scientific icap 7000 Plus Series ICP-OES. Gain more power. experience more performance
Thermo Scientific icap 7000 Plus Series ICP-OES Gain more power experience more performance Thermo Scientific icap 7000 Plus Series ICP-OES Powerful, easy-to-use, solution for multi-element analysis Maximize
More informationThe Assessment Survey - Key elements
The Assessment Survey - Key elements Lecture 2 IH&S 725 Instructor Steven Guffey, PhD, C.I.H. Slides originally developed by Warren Myers, PhD 1 Goals of the assessment survey 1 identify, measure and control
More informationPharmaceutical Waste Management (Clinics) Waste Management Operations. Coordination, Evaluation, Monitoring
CHEMICAL AND RADIOACTIVE WASTES MANAGEMENT PLAN 2018 I. Introduction The Chemical and Radioactive Wastes Management Plan defines the mechanisms for oversight in controlling potential exposures to chemical
More information2019 MANAGEMENT PLAN FOR CHEMICAL AND RADIOACTIVE WASTES
2019 MANAGEMENT PLAN FOR CHEMICAL AND RADIOACTIVE WASTES I. Introduction The Chemical and Radioactive Wastes Management Plan defines the mechanisms for oversight in controlling potential exposures to chemical
More informationDESIGNING AND IMPLEMENTING A LIFE-CYCLE COST MODEL FOR FIRST-OF- A-KIND BUILDING DECOMMISSIONING
DESIGNING AND IMPLEMENTING A LIFE-CYCLE COST MODEL FOR FIRST-OF- A-KIND BUILDING DECOMMISSIONING Jeffrey Stevens Robert Williamson Allen Schubert Kaiser Hill, L.L.C. R. F. Shangraw, Jr. Project Performance
More information2 / 1. SUMMARY public, should be well documented, and should be reviewed on a regular basis to determine whether it continues to meet the operational
1. Summary This Report is concerned with the protection of individuals who may be exposed to radiation emitted by x-ray equipment and both sealed and unsealed radioactive sources in the practice of veterinary
More informationA69 Checklist for Bulk Asbestos Revision 1.2 May 5, 2015
A69 Checklist for Bulk Asbestos Revision 1.2 May 5, 2015 Laboratory Name: Appendix Name: Appendix Number: Assessor: Date: 01 DOCUMENT CONTROL 01 4.3 : is there a documented method? : Verify that the current
More informationTreatment of Spent Nuclear Fuel with Molten Salts
Treatment of Spent Nuclear Fuel with Molten Salts Michael Goff Deputy Associate Laboratory Director Operations Nuclear Science and Technology Idaho National Laboratory 2008 Joint Symposium on Molten Salts
More informationDOE ORDER "RADIOACTIVE WASTE MANAGEMENT" SRS & DOE COMPLEX IMPLEMENTATION ISSUES AND COSTS. W.T. Goldston Westinghouse Savannah River Company
ABSTRACT DOE ORDER 435.1 "RADIOACTIVE WASTE MANAGEMENT" SRS & DOE COMPLEX IMPLEMENTATION ISSUES AND COSTS W.T. Goldston Westinghouse Savannah River Company The Department of Energy (DOE) plans to issue
More informationFuel Savings for Gas Power Plants. Using Digital Efficiency and Flexibility Optimization
Fuel Savings for Gas Power Plants Using Digital Efficiency and Flexibility Optimization High Fuel Impact Gas Plant Operations Utilities and power generators today face the difficult task of servicing their
More informationUnit 3: Elements of a Viable Continuity Capability
Unit 3: Elements of a Viable Continuity Capability Unit 3 Objectives Identify all organization essential functions and their effect upon staffing levels in a continuity event. Recognize and incorporate
More informationJ. M. Giaquinto J. M. Keller A. M. Meek Oak Ridge National Laboratory Oak Ridge, TN
Inductively Coupled Plasma Mass Spectrometer Installation Modifications in a Radioactive Contaminated Laboratory for the Analysis of DOE Radioactive Waste Streams J. M. Giaquinto J. M. Keller A. M. Meek
More information