Winter Meeting & Expo
Total Page:16
File Type:pdf, Size:1020Kb
Load more
Recommended publications
-
Graphite Materials for the U.S
ANRIC your success is our goal SUBSECTION HH, Subpart A Timothy Burchell CNSC Contract No: 87055-17-0380 R688.1 Technical Seminar on Application of ASME Section III to New Materials for High Temperature Reactors Delivered March 27-28, 2018, Ottawa, Canada TIM BURCHELL BIOGRAPHICAL INFORMATION Dr. Tim Burchell is Distinguished R&D staff member and Team Lead for Nuclear Graphite in the Nuclear Material Science and Technology Group within the Materials Science and Technology Division of the Oak Ridge National Laboratory (ORNL). He is engaged in the development and characterization of carbon and graphite materials for the U.S. Department of Energy. He was the Carbon Materials Technology (CMT) Group Leader and was manager of the Modular High Temperature Gas-Cooled Reactor Graphite Program responsible for the research project to acquire reactor graphite property design data. Currently, Dr. Burchell is the leader of the Next Generation Nuclear Plant graphite development tasks at ORNL. His current research interests include: fracture behavior and modeling of nuclear-grade graphite; the effects of neutron damage on the structure and properties of fission and fusion reactor relevant carbon materials, including isotropic and near isotropic graphite and carbon-carbon composites; radiation creep of graphites, the thermal physical properties of carbon materials. As a Research Officer at Berkeley Nuclear Laboratories in the U.K. he monitored the condition of graphite moderators in gas-cooled power reactors. He is a Battelle Distinguished Inventor; received the Hsun Lee Lecture Award from the Chinese Academy of Science’s Institute of Metals Research in 2006 and the ASTM D02 Committee Eagle your success is our goal Award in 2015. -
Rulemaking for Enhanced Security of Special Nuclear Material
Rulemaking for Enhanced Security of Special Nuclear Material RIN number: 3150-AJ41 NRC Docket ID: NRC-2014-0118 Regulatory Basis Document January 2015 Table of Contents 1. Introduction and Background .............................................................................................. 1 2. Existing Regulatory Framework .......................................................................................... 3 2.1 Regulatory History ............................................................................................................. 3 2.2 Existing Regulatory Requirements .................................................................................... 8 3. Regulatory Problem .......................................................................................................... 13 3.1 Generic Applicability of Security Orders .......................................................................... 13 3.2 Risk Insights .................................................................................................................... 16 3.3 Consistency and Clarity .................................................................................................. 27 3.4 Use of a Risk-Informed and Performance-Based Structure. ........................................... 29 4. Basis for Requested Changes ........................................................................................... 30 4.1 Material Categorization and Attractiveness ..................................................................... 30 4.2 -
Pennsylvania. Prior to Joining Westinghouse in 1969, He Was
Pennsylvania. Prior to joining Westinghouse in 1969, he was by the corporation almost since its inception, at the con- associated with the University of Pisa and the Italian Fast clusion of the story (1977) one is left with the feeling that Breeder Reactor Program. Dr. Carelli serves also as adjunct Kerr-McGee is a corporation whose officers have dared to faculty professor at the University of Pittsburgh, where he make some bold decisions-to take the risks-and have teaches courses in nuclear technology. He is a recognized received handsome rewards, not only for the stockholders expert in liquid-metal fast breeder reactor (LMFBR) core and employees, but for the economic benefit of the citizens design and liquid-metal heat transfer and fluid flow; he has of the U.S. authored over 50 publications in these areas. Dr. Carelli is an active member of the American Nuclear Society and Dr. J. N. Anno is a professor of nuclear engineering of the International Association for Hydraulic Research, at the University of Cincinnati and president of Research where he is responsible for program activities in LMFBR Dynamics Incorporated, a small research and development core thermal hydraulics. corporation. He has spent over 25 years in research and development activities, much of that in energy-related areas. From 1953 to 1970, he was employed by Battelle Memorial Institute, Columbus, Ohio, where he was engaged Innovations in Energy: The Story of Kerr-McGee in primarily nuclear-oriented research. He is the co-inventor on four U.S. patents concerning a novel heat engine, and Author John Samuel Ezell currently is active in materials research and production for fusion reactor blankets. -
Winter Meeting & Expo
Winter Meeting & Expo 2017 Official Program Generations in Collaboration: Building for Tomorrow October 29-November 2, 2017 Washington, D.C. Marriott Wardman Park Winter Meeting & Expo Our most sincere thanks to our sponsors for their support of the 2017 Winter Meeting & Expo. GOLD SPONSORSHIP BRONZE SPONSORSHIP COPPER SPONSORSHIP OTHER SPONSORSHIP Table of Contents GENERAL MEETING INFORMATION Organizing Committee ................................................................................ 2 Daily Schedule .......................................................................................... 3-6 General Information .................................................................................. 7-10 PLENARY, SPECIAL SESSIONS & EVENTS Young Professionals Congress Sessions . ...................................................... 11 ANS President’s Opening Reception ........................................................... 11 Opening Plenary Session ........................................................................... 11 ANS President’s Special Session ................................................................ 11 Operations & Power Division Dinner ............................................................ 11 Student Poster Session ............................................................................. 12 General Chair’s Special Session ................................................................. 12 Speakers Bureau Workshop ........................................................................ 12 Focus -
Regulations for the Control of Radiation in Mississippi Rule 1.1.18 for Applicable Fee
Title 15: Mississippi State Department of Health Part 21: Division of Radiological Health Subpart 78: Radiological Health Chapter 1 REGULATIONS FOR CONTROL OF RADIATION IN MISSISSIPPI Subchapter 1 General Provisions Rule 1.1.1 Scope. Except as otherwise specifically provided, these regulations apply to all persons who receive, possess, use, transfer, own, or acquire any source of radiation; provided, however, that nothing in these regulations shall apply to any person to the extent such person is subject to regulation by the U.S. Nuclear Regulatory Commission.1 SOURCE: Miss. Code Ann. §45-14-11 Rule 1.1.2 Definitions. As used in these regulations, these terms have the definitions set forth below. Additional definitions used only in a certain section will be found in that section. 1. "A1" means the maximum activity of special form radioactive material permitted in a Type A package. "A2" means the maximum activity of radioactive material, other than special form, LSA and SCO material, permitted in a Type A package. These values are either listed in Appendix A, Table A-1 of Subchapter 13 of these regulations or may be derived in accordance with the procedure prescribed in Appendix A of Subchapter 13 of these regulations. 2. "Absorbed dose" means the energy imparted to matter by ionizing radiation per unit mass of irradiated material at the place of interest. The units of absorbed dose are the rad and the gray (Gy). 3. "Accelerator" means any machine capable of accelerating electrons, protons, deuterons, or other charged particles in a vacuum and of discharging the resultant particulate or other radiation into a medium at energies usually in excess of 1 MeV. -
Mariah M. Ramirez [email protected] College Station, TX
Mariah M. Ramirez [email protected] College Station, TX. 77840 Citizenship: US Citizen Education Texas A&M University, College Station, TX. August 2017 – December 2022 Masters of Science in Nuclear Engineering Overall GPA: 3.88/4.00 Certificate from the Center for Nuclear Security Science & Policy Initiatives (NSSPI) Graduate Advisor: Dr. Sunil Chirayath & Dr. Charles M. Folden III The University of Texas (UT), Austin, TX. July 2013 – May 2017 Bachelor of Science in Physics Overall GPA: 3.43/4.00 Radiation Physics Option, six courses in Nuclear and Radiation Engineering Certificate in Forensic Science Research Experience Center for Nuclear Security Science and Policy Initiatives (NSSPI) June 2018 – Present Texas A&M University, College Station, TX. Graduate Research Assistant Graduate Advisor: Dr. Sunil Chirayath, Director of NSSPI and Associate Professor Thesis Title: Safeguards Analysis for Neptunium-237 in High-Level Used Fuel Waste Through Computational and Radiochemical Methods • Conduct literary research and review on neptunium extraction and reprocessing work for safeguards • Analyze and quantify how much neptunium is produced from various reactor and fuel types • Conduct chemical separation processes to analyze separation methods for neptunium Undergraduate Research Assistant at the Nuclear Engineering Teaching Laboratory (NETL) University of Texas, Austin, TX. February 2016 – July 2017 Supervisor: Dr. Steven Biegalski, Former Director of NETL and Academic Program Professor Current Nuclear and Radiological Engineering and -
602 Public Law 88-4S8~Aug. 22, 1964 [78 Stat
602 PUBLIC LAW 88-4S8~AUG. 22, 1964 [78 STAT. such agency, if the assistance or progam will promote the welfare of the Trust Territory, notwithstanding any provision of law under which the Trust Territory may otherwise be ineligible for the assist ance or program: Provided^ That the Secretary of the Interior shall not request assistance pursuant to this subsection that involves, in the aggregate, an estimated nonreimbursable cost in any one fiscal year in excess of $150,000: Provided further. That the cost of any program extended to the Trust Territory under this subsection shall be reim bursable out of appropriations authorized and made for the govern 48 use 1681 note. ment of the Trust Territory pursuant to section 2 of this Act, as amended. The provisions of this subsection shall not apply to finan cial assistance under a grant-in-aid program." SEC. 2. Subsection 303(1) of the Communications Act of 1934 (48. 76 Stat. 64. Stat. 1082), as amended (47 U.S.C. 303(1)), is hereby amended by inserting the words: ", or citizens of the Trust Territory of the Pacific Islands presenting valid identity certificates issued by the High Com missioner of such Territory," immediately following the words "citi zens or nationals of the United States". Revolving fund, abolishment. SEC. 3. The revolving fund authorized by the Department of the Interior and Related Agencies Appropriation Act, 1956 (69 Stat. 141, 149), to be available during fiscal year 1956 for loans to locally owned private training companies in the Trust Territory of the Pacific Islands, which revolving fund has been continued by subsequent annual appropriation Acts, is hereby abolished, and the total assets of the revolving fund are contributed as a grant to the government of the Trust Territory for use as a development fund within the Trust Territory of the Pacific Islands. -
Nuclear Regulatory Commission § 70.5
Nuclear Regulatory Commission § 70.5 section 51 of the act, determines to be intermediates, which are unsuitable for special nuclear material, but does not use in their present form, but all or include source material; or (2) any ma- part of which will be used after further terial artificially enriched by any of processing. the foregoing but does not include Strategic special nuclear material source material; means uranium-235 (contained in ura- Special nuclear material of low strategic nium enriched to 20 percent or more in significance means: the U235 isotope), uranium-233, or pluto- (1) Less than an amount of special nium. nuclear material of moderate strategic Transient shipment means a shipment significance as defined in paragraph (1) of nuclear material, originating and of the definition of strategic nuclear terminating in foreign countries, on a material of moderate strategic signifi- vessel or aircraft which stops at a cance in this section, but more than 15 United States port. grams of uranium-235 (contained in Unacceptable performance deficiencies uranium enriched to 20 percent or more mean deficiencies in the items relied in U-235 isotope) or 15 grams of ura- on for safety or the management meas- nium-233 or 15 grams of plutonium or ures that need to be corrected to en- the combination of 15 grams when com- sure an adequate level of protection as puted by the equation, grams = (grams defined in 10 CFR 70.61(b), (c), or (d). contained U-235) + (grams plutonium) + United States, when used in a geo- (grams U-233); or graphical sense, includes Puerto Rico (2) Less than 10,000 grams but more and all territories and possessions of than 1,000 grams of uranium-235 (con- the United States. -
State-Of-The-Art Mobile Radiation Detection Systems for Different Scenarios
sensors Review State-of-the-Art Mobile Radiation Detection Systems for Different Scenarios Luís Marques 1,* , Alberto Vale 2 and Pedro Vaz 3 1 Centro de Investigação da Academia da Força Aérea, Academia da Força Aérea, Instituto Universitário Militar, Granja do Marquês, 2715-021 Pêro Pinheiro, Portugal 2 Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, Av. Rovisco Pais 1, 1049-001 Lisboa, Portugal; [email protected] 3 Centro de Ciências e Tecnologias Nucleares, Instituto Superior Técnico, Universidade de Lisboa, Estrada Nacional 10 (km 139.7), 2695-066 Bobadela, Portugal; [email protected] * Correspondence: [email protected] Abstract: In the last decade, the development of more compact and lightweight radiation detection systems led to their application in handheld and small unmanned systems, particularly air-based platforms. Examples of improvements are: the use of silicon photomultiplier-based scintillators, new scintillating crystals, compact dual-mode detectors (gamma/neutron), data fusion, mobile sensor net- works, cooperative detection and search. Gamma cameras and dual-particle cameras are increasingly being used for source location. This study reviews and discusses the research advancements in the field of gamma-ray and neutron measurements using mobile radiation detection systems since the Fukushima nuclear accident. Four scenarios are considered: radiological and nuclear accidents and emergencies; illicit traffic of special nuclear materials and radioactive -
SENATE BILL No. 125
{As Amended by Senate Committee of the Whole} Session of 2015 SENATE BILL No. 125 By Committee on Natural Resources 2-2 1 AN ACT concerning radioactive materials; relating to by-product material; 2 low-level radioactive waste; naturally occurring radioactive material; 3 amending K.S.A. 48-1603 and 48-1620 and repealing the existing 4 sections. 5 6 Be it enacted by the Legislature of the State of Kansas: 7 Section 1. K.S.A. 48-1603 is hereby amended to read as follows: 48- 8 1603. As used in this act: 9 (a) "By-product material" means: (1) Any radioactive material, except 10 special nuclear material, yielded in or made radioactive by exposure to the 11 radiation incident to the process of producing or utilizing special nuclear 12 material; and 13 (2) the tailings or wastes produced by the extraction or concentration of 14 uranium or thorium from any ore processed primarily for its source 15 material content; 16 (3) any discrete source of radium-226 that is produced, extracted or 17 converted after extraction for use for a commercial, medical or research 18 activity; and 19 (4) any material that: 20 (A) Has been made radioactive by use of a particle accelerator; and 21 (B) is produced, extracted or converted after extraction for use for a 22 commercial, medical or research activity; or 23 (5) any discrete source of naturally occurring radioactive material, 24 other than source material, that: 25 (A) The secretary declares by order would pose a threat to the public 26 health and safety or the common defense and security similar to the threat 27 posed by a discrete source of radium-226 after the United States nuclear 28 regulatory commission, or any successor thereto, determines the same; 29 and 30 (B) is extracted or converted after extraction for use in a commercial, 31 medical or research activity. -
Steven Biegalski: NEDHO's Role in Nuclear
Education & Training Special Section THE NUCLEAR NEWS INTERVIEW Steven Biegalski: NEDHO’s role in nuclear engineering education The Nuclear Engineering Department Heads Organization provides a forum for addressing issues affecting nuclear engineering programs at U.S. colleges and universities. teven Biegalski is the current What is the state of NEDHO today? How many members? Who is eligible to chair of the Nuclear Engineer- join NEDHO? ing Department Heads Organi- Currently, we have 28 full members and S 16 associate members. Full members pay zation (NEDHO), a group formed in dues and have voting privileges. Associ- 1982 to provide a forum for discus- ate members participate in meetings but do not pay dues or have voting privileg- sion, coordination, and collabora- es. It’s an institutional membership, so tion among university nuclear engi- an individual faculty member is not eligi- ble to join. neering department chairs on issues We’re open to any university in North concerning nuclear and radiological America with a nuclear engineering pro- gram. We do have some institutions, par- engineering programs. Among the ticularly the military academies, that ar- issues that NEDHO deals with are en’t allowed to pay dues. They still come and participate in the meetings, which is the accreditation of academic pro- great. It’s just that the caveat is if they’re grams, funding for scholarships and not paying dues, they don’t have voting privileges. Most of the votes are for bud- fellowships, research funding and geting—for example, giving funds to the ANS Young Members Group. So if you’re opportunities, and funding for train- Biegalski: “I am happy to report that the not paying dues into NEDHO, you’re job prospects for our students appear very ing and research reactors. -
American Nuclear Society
ORNL/TM-2011/402 Oak Ridge National Laboratory Next-Generation Safeguards Initiative October 2011 Prepared by Bernadette L. Kirk Dawn Eipeldauer Michael Whitaker DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge. Web site http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source. National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Web site http://www.ntis.gov/support/ordernowabout.htm Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange (ETDE) representatives, and International Nuclear Information System (INIS) representatives from the following source. Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Web site http://www.osti.gov/contact.html This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof.