RESUME John L. Liebenthal
208/354-8001
e-mail: jll@tetontel.com
Feb98-Apr99 Consultant For EG&G Technical Services: Arthur Anderson/Venable team for Lockheed Martin Environmental. Legal support--Technical review of nuclear safety activities and documentation for Pit 9 Project.
Jan93- Dec97 Consultant:
For Global Technology Inc. Review and recommendation concerning hazard categorization for WRAP 1 Facility, Hanford.
For H&R Technical Associates: Reviewer with Senior Review Board, Chair of Independent review panel of MSRE (ORNL) Remediation Project, involving migration and cleanup of U233F6.
For Belfort Engineering and Environmental Services: Review of SAR Implementation Plans for EM. Follow-up of tasks for ER SAR/TSR review and NE SAR training materials.
All the following experience is with EG&G, Idaho, Inc, and predecessor companies at the INEL/NRTS site.
Jun91-Jan93 Senior Technical Advisor: Assistance to DOE Energy Research Office of Assessment and Support: Safety Analysis Report (SAR) and Technical Safety Requirements (TSR) consulting; led Energy Research non-DOE team reviewing Tokamak Fusion Test Reactor SAR for ER-8, Office of Energy Research Office of Assessment and Support, coordinating ER-8 contractors reviewing the SAR and OSRs for tritium operation of the TFTR (Tokamak Fusion Test Reactor) including worker safety, electrical safety, toxic releases, radiation protection, and public safety. Work for Office of Nuclear Energy Office of Standards and Policy involved development of training for Operations Office and Field Office personnel in preparation of SARs to the requirements of DOE Order 5480.23, Safety Analysis Reports. Participation in review of the process and effectiveness of implementation of DOE Orders and Rules, particularly those involving SARs, TSRs, and USQs. Preparation of SAR training course.
Founding member of Energy Facilities Contractors Operating Group's Safety Analysis Working Group.
Sep87-Jun91 DOE Support: Management and participation in 13 M$ of support projects to DOE HQ. Established programs for DOE Office of Safety and Quality, in Electrical Safety, Fire Protection, Hoisting and Rigging. Support of DOE-DP in Equipment Inspection and Equipment Testing, system and component reviews.
Staffing DOE on-site reviews: Technical Safety Appraisals, Quality Appraisals.
Tiger Teams and Technical Safety Appraisals (TSAs). Participated in
TSA Purex (Hanford)--Auxiliary Systems.
4 person H&S Tiger Team, Y12 -- Engineering, Major Modifications. Served as acting H&S Team leader for report and closeout phase
Tiger Team, Sandia Livermore -- Technical Support, Auxiliary Systems
Continuation of Savannah River review started in March 1987: Core Thermal Hydraulics, INEL dryout experiments in annuli flooded from above, review of analytical methods for core and system analysis, system modifications, safety documentation.
May86-Sep87 Post Chernobyl reviews of DOE facilities:
N Reactor Special Review May 1986 - Confinement Sub-Team Leader.
Design Reviews June-September 1986: N Reactor, HFIR, and Savannah River Reactors.
First independent review of Savannah River Reactor L Reactor derating and emergency core cooling, core thermal hydraulics, system dynamics.
Contractor coordinator of DOE-led Special Review of Savannah River Reactor technical support, core analysis and implementation, system engineering, design, structural analysis, electronic engineering.
The first review of Savannah River P- Reactor reactivity anomaly, which resulted in shutdown.
Review of N-reactor confinement hydrogen modifications and other plant modifications.
1983-Feb87 Manager, Chemical Process Engineering Branch: (partially concurrent with the entry above) Managed organizaiton engaged in the following:
Process engineering for Radioactive Waste Management, Industrial Energy Conservation, Idaho Chemical Processing Plant, Air Force Toxic Waste Management.
Energy analysis of power cycles, thermodynamic modeling of nuclear rocket propulsion concepts.
Company representative to Heat Transfer Research, Inc., and Cooling Tower Institute.
1973-1983 Manager, Thermal Analysis Branch: Broadest possible applications in compressible and incompressible fluid dynamics; heat transfer: finite element and finite difference conduction, convection, boiling. Code development, application of large codes. Reactor safety, core analysis, fuels engineering.
Thermal analysis of structures for ASME Section III structural analysis.
Thermodynamic analysis of heat recovery, geothermal, innovative power cycles. Analysis of fusion plasma disruptions; fusion system concepts.
Conceptual design of ultra high flux reactor, patented features of were part of the Advanced Neutron Source reactor design.
Pre-conceptual design of nuclear rocket test facilities.
1970-1973 Manager, Nuclear Engineering and Analysis: System and component thermal hydraulics,, SARs, structural analysis and structural dynamics, materials engineering for test reactor and non-reactor facilities, nuclear reactor core and system analysis and safety core safety analysis, engineering support to fuel procurement.
1966-1970 Supervisor, Heat Transfer, Hydraulics, and Radiography: Test reactor support, core and system thermal hydraulics, fuel procurement and inspection experimental, analytical, ASME structural and piping analysis, structure and heat exchanger flow induced vibration, welder qualification, weld inspection, NDE, test reactor fuel procurement engineering, reactor system in-service testing. Member of test reactor facility safety review.
1964-1966 Process Engineering Supervisor, Test Reactor Area and Test Area North: Engineering of reactor fuel, auxiliary systems, repair and modification, inspection program for all NRTS (INEL) ASME code vessels, cranes, and boilers, safety analysis and conceptual design of new facilities, review of AE design of ATR reactor, process systems, auxiliaries, component and system tests. PM2A reactor vessel fracture toughness burst test, SAR for Piqua Organic Cooled Reactor hydrocracking coolant purification system.
1957-1964 Plant Engineer, Test Reactors: Thermal hydraulics, shielding, reactor safety, thermal stress analysis, core surveillance, fuel qualification and procurement, process systems, conceptual design of test and organic reactors, Safety Analysis Reports.
EDUCATION BS, MS, Chemical Engineering, Purdue University
PATENT
4,764,339 High Flux Reactor. Co-inventor. Includes the split core concept upon which the Advanced Neutron Source design was based.
PUBLICATIONS
"The Effect of Gamma Radiation on the Low Temperature Oxidation of Propane" J. L. Liebenthal and L. F. Albright. Proceedings of the Second United Nations Conference on the Peaceful Uses of Atomic Energy, 29, pp. 107-112. (1958)
"Beryllium Cracking of the Advanced Test Reactor", E. H. Smith, J. L. Liebenthal, B. V. Winkel, J. M. Beeston, and W. C. Francis, Symposium on Materials Performance in Operating Nuclear Reactors, (1973)
"Entrained Liquid Behavior in a PWR Upper Plenum and Steam Generator during the Reflood Phase of the LOCA", R. A. Livingston, K. M. Peery, W. C. Kettenacker, E. C. Lemmon, and J. L. Liebenthal, ANS Topical Meeting on Thermal Reactor Safety (1977)
"Experiments on Hydrogen for Three Mile Island", R. L. Wooley, J. H. Ruckman, G. L. Kimball, A. L. Ayers Jr., and J. L. Liebenthal, ANS Topical Meeting on Reactor Safety. (1980).
"Ultrahigh Flux Reactor Design Probing the Limits of Plate Fuel Technology", J. A. Lake, D. K. Parsons, J. L. Liebenthal, J. M. Ryskamp, G. N. Fillmore, and D. R. Deboisblanc, Nuclear Instruments and Methods in Physics Research, A249 No. 1, pp. 41-52, 1986.
"Requirements, Needs, and Concepts for a New Broad Application Test Reactor", J. M. Ryskamp, C. D. Fletcher, A. B. Denison, and J. L. Liebenthal, Transactions of ANS, 1992, pp. 165-7.
208/354-8001
e-mail: jll@tetontel.com
Feb98-Apr99 Consultant For EG&G Technical Services: Arthur Anderson/Venable team for Lockheed Martin Environmental. Legal support--Technical review of nuclear safety activities and documentation for Pit 9 Project.
Jan93- Dec97 Consultant:
For Global Technology Inc. Review and recommendation concerning hazard categorization for WRAP 1 Facility, Hanford.
For H&R Technical Associates: Reviewer with Senior Review Board, Chair of Independent review panel of MSRE (ORNL) Remediation Project, involving migration and cleanup of U233F6.
For Belfort Engineering and Environmental Services: Review of SAR Implementation Plans for EM. Follow-up of tasks for ER SAR/TSR review and NE SAR training materials.
All the following experience is with EG&G, Idaho, Inc, and predecessor companies at the INEL/NRTS site.
Jun91-Jan93 Senior Technical Advisor: Assistance to DOE Energy Research Office of Assessment and Support: Safety Analysis Report (SAR) and Technical Safety Requirements (TSR) consulting; led Energy Research non-DOE team reviewing Tokamak Fusion Test Reactor SAR for ER-8, Office of Energy Research Office of Assessment and Support, coordinating ER-8 contractors reviewing the SAR and OSRs for tritium operation of the TFTR (Tokamak Fusion Test Reactor) including worker safety, electrical safety, toxic releases, radiation protection, and public safety. Work for Office of Nuclear Energy Office of Standards and Policy involved development of training for Operations Office and Field Office personnel in preparation of SARs to the requirements of DOE Order 5480.23, Safety Analysis Reports. Participation in review of the process and effectiveness of implementation of DOE Orders and Rules, particularly those involving SARs, TSRs, and USQs. Preparation of SAR training course.
Founding member of Energy Facilities Contractors Operating Group's Safety Analysis Working Group.
Sep87-Jun91 DOE Support: Management and participation in 13 M$ of support projects to DOE HQ. Established programs for DOE Office of Safety and Quality, in Electrical Safety, Fire Protection, Hoisting and Rigging. Support of DOE-DP in Equipment Inspection and Equipment Testing, system and component reviews.
Staffing DOE on-site reviews: Technical Safety Appraisals, Quality Appraisals.
Tiger Teams and Technical Safety Appraisals (TSAs). Participated in
TSA Purex (Hanford)--Auxiliary Systems.
4 person H&S Tiger Team, Y12 -- Engineering, Major Modifications. Served as acting H&S Team leader for report and closeout phase
Tiger Team, Sandia Livermore -- Technical Support, Auxiliary Systems
Continuation of Savannah River review started in March 1987: Core Thermal Hydraulics, INEL dryout experiments in annuli flooded from above, review of analytical methods for core and system analysis, system modifications, safety documentation.
May86-Sep87 Post Chernobyl reviews of DOE facilities:
N Reactor Special Review May 1986 - Confinement Sub-Team Leader.
Design Reviews June-September 1986: N Reactor, HFIR, and Savannah River Reactors.
First independent review of Savannah River Reactor L Reactor derating and emergency core cooling, core thermal hydraulics, system dynamics.
Contractor coordinator of DOE-led Special Review of Savannah River Reactor technical support, core analysis and implementation, system engineering, design, structural analysis, electronic engineering.
The first review of Savannah River P- Reactor reactivity anomaly, which resulted in shutdown.
Review of N-reactor confinement hydrogen modifications and other plant modifications.
1983-Feb87 Manager, Chemical Process Engineering Branch: (partially concurrent with the entry above) Managed organizaiton engaged in the following:
Process engineering for Radioactive Waste Management, Industrial Energy Conservation, Idaho Chemical Processing Plant, Air Force Toxic Waste Management.
Energy analysis of power cycles, thermodynamic modeling of nuclear rocket propulsion concepts.
Company representative to Heat Transfer Research, Inc., and Cooling Tower Institute.
1973-1983 Manager, Thermal Analysis Branch: Broadest possible applications in compressible and incompressible fluid dynamics; heat transfer: finite element and finite difference conduction, convection, boiling. Code development, application of large codes. Reactor safety, core analysis, fuels engineering.
Thermal analysis of structures for ASME Section III structural analysis.
Thermodynamic analysis of heat recovery, geothermal, innovative power cycles. Analysis of fusion plasma disruptions; fusion system concepts.
Conceptual design of ultra high flux reactor, patented features of were part of the Advanced Neutron Source reactor design.
Pre-conceptual design of nuclear rocket test facilities.
1970-1973 Manager, Nuclear Engineering and Analysis: System and component thermal hydraulics,, SARs, structural analysis and structural dynamics, materials engineering for test reactor and non-reactor facilities, nuclear reactor core and system analysis and safety core safety analysis, engineering support to fuel procurement.
1966-1970 Supervisor, Heat Transfer, Hydraulics, and Radiography: Test reactor support, core and system thermal hydraulics, fuel procurement and inspection experimental, analytical, ASME structural and piping analysis, structure and heat exchanger flow induced vibration, welder qualification, weld inspection, NDE, test reactor fuel procurement engineering, reactor system in-service testing. Member of test reactor facility safety review.
1964-1966 Process Engineering Supervisor, Test Reactor Area and Test Area North: Engineering of reactor fuel, auxiliary systems, repair and modification, inspection program for all NRTS (INEL) ASME code vessels, cranes, and boilers, safety analysis and conceptual design of new facilities, review of AE design of ATR reactor, process systems, auxiliaries, component and system tests. PM2A reactor vessel fracture toughness burst test, SAR for Piqua Organic Cooled Reactor hydrocracking coolant purification system.
1957-1964 Plant Engineer, Test Reactors: Thermal hydraulics, shielding, reactor safety, thermal stress analysis, core surveillance, fuel qualification and procurement, process systems, conceptual design of test and organic reactors, Safety Analysis Reports.
EDUCATION BS, MS, Chemical Engineering, Purdue University
PATENT
4,764,339 High Flux Reactor. Co-inventor. Includes the split core concept upon which the Advanced Neutron Source design was based.
PUBLICATIONS
"The Effect of Gamma Radiation on the Low Temperature Oxidation of Propane" J. L. Liebenthal and L. F. Albright. Proceedings of the Second United Nations Conference on the Peaceful Uses of Atomic Energy, 29, pp. 107-112. (1958)
"Beryllium Cracking of the Advanced Test Reactor", E. H. Smith, J. L. Liebenthal, B. V. Winkel, J. M. Beeston, and W. C. Francis, Symposium on Materials Performance in Operating Nuclear Reactors, (1973)
"Entrained Liquid Behavior in a PWR Upper Plenum and Steam Generator during the Reflood Phase of the LOCA", R. A. Livingston, K. M. Peery, W. C. Kettenacker, E. C. Lemmon, and J. L. Liebenthal, ANS Topical Meeting on Thermal Reactor Safety (1977)
"Experiments on Hydrogen for Three Mile Island", R. L. Wooley, J. H. Ruckman, G. L. Kimball, A. L. Ayers Jr., and J. L. Liebenthal, ANS Topical Meeting on Reactor Safety. (1980).
"Ultrahigh Flux Reactor Design Probing the Limits of Plate Fuel Technology", J. A. Lake, D. K. Parsons, J. L. Liebenthal, J. M. Ryskamp, G. N. Fillmore, and D. R. Deboisblanc, Nuclear Instruments and Methods in Physics Research, A249 No. 1, pp. 41-52, 1986.
"Requirements, Needs, and Concepts for a New Broad Application Test Reactor", J. M. Ryskamp, C. D. Fletcher, A. B. Denison, and J. L. Liebenthal, Transactions of ANS, 1992, pp. 165-7.
