DOCSLIB.ORG

Proceedings of the 1984 Doe Nuclear Reactor and Facility Safety Conference

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Proceedings of the 1984 Doe Nuclear Reactor and Facility Safety Conference .- 0221-1, CONF-840257(Vol. 2) (DE84012694) COUF-24C257—Vol.2 DE84 0126 94 PROCEEDINGS OF THE 1984 DOE NUCLEAR REACTOR AND FACILITY SAFETY CONFERENCE Rockville, Maryland February 27-March 1, 1984 VOLUME I! U.S. Department of Energy Office of Nuclear Safety CONF-840257(Voi. 2) (DE84012694) Distribution Category UC-41 PROCEEDINGS OF THE 1984 DOE NUCLEAR REACTOR AND FACILITY SAFETY CONFERENCE Rockville, Maryland February 27-March 1, 1984 VOLUME II U.S. Department of Energy Office of Nuclear Safety Published by Technical Information Center Office of Scientific and Technical Information United States Department of Energy . These proceedings were compiled under contract number DE-ACO5-76OR00O33 be- tween the U.S. Department of Energy, Office of Nuclear Safety, and Oak Ridge Associ- ated Universities. TABLE OF CONTENTS VCLUME I Preface - vii Monday, February 27, 1984 CNS Overview 3 J. Maher - U.S. Department of Energy, Office of Nuclear Safety Activities e»id Projects r. 31 P., Barber - U.S., Department of Energy, Office of Nuclear Safety QNS/RC Emergency Activitj.es 59 J. Deal - U.S, Department of Energy, Office of Nuclear Safety Potential Conflict Between Safeguards/Security and Safety 69 N. Klug - U.S. Department of Energy, Nuclear Energy Proposed Changes in Regulatory Standards Effect on DOE ,.... 79 W. Brynda - Brookhaven National Laboratory Impact, of Post TMI-2 Cleanup Activities on Cleanup and Decommissioning of DOE Facilities 105 H. Burton - EG&G Idaho, Inc. ASPE/ESS.H Ranarks , 135 J. Mares - Assistant Secretary for Policy and Environment, U.S. Department of Energy R. Davit's - Deputy Assistant Secretary for Environment, Safety, and Health, U.S. Department of Energy Technical Specifications and Operational Safety Requirements Panel T. Dahl - Oak Ridge National Laboratory 137 L. Durney - EG&G Idaho, Inc c 155 G. McRae - Union Carbide Corporation, Oak Ridge Gaseous Diffusion Plant 165 Space Reactor Systems and Safety Strategies 177 D. Bunch - U.S. Department of Energy, Office of Space Reactor Projects Probabilistic Risk Assessment W. Durant - I. E. Dupont de Nemours and Company .. = 181 W. Perkins - I.E. Dupont de Nanours and Company 185 What is a Practical Risk Assessment? 195 E. Howard - Los Alamos National Laboratory Tuesday, February 28, 1984 ORR Activities: Rockwell Hanford 199 A. Hawkins - Rockwell Hanf ord Operations ORR Activities: PUREX , 217 M. Zamorski - U.S. Department of Energy, Richland Operations Office ORR Activities: "Nn Reactor 219 P. Carlson - UNC Nuclear Industries, Inc. ORR Activities: ACRR Upgrade 233 J. Philbin - Sandia National Laboratories, Albuquerque F. Morris - Sandia National Laboratories, Albuquerque T. Luera - Sandia National Laboratories, Albuquerque ORR Activities: "L" Reactor 243 R. Finley - I.E. Dupont de Nemours and Company ORR Activities: nLn Reactor 259 J. Anderson - U.S. Department of Energy, Savannah River Operations Office VOLUME II Program Line Safety Reviews of Savannah River SARF 271 J. Koelling - Los Alamos National Laboratory Safety Review of Experiments 283 K. Elliott - U.S. Department of Energy, Albuquerque Operations Office Overview of Criticality Safety *,. 291 B. Brown - U.S. Department of Energy, Office of Nuclear Safety Nuclear Criticality Technology and Safety Project 319 J. Thomas - Oak Ridge National Laboratory Radiological Accident Considerations 323 J. Graf - Los Alamos National Laboratory Radiological Accident Considerations 329 J. Elder - Los Alamos National Laboratory Wednesday, February 2S, 1984 Overview of TRADE t „ 343 C. LMinelli - Rockwell International, Rocky Flats Plant Reactor Training Coordination Program 351 E. Treat - EG&G Idaho, Inc. IV Overview of Job and Task Analysis • 365 D. Gertman - EG&G Idaho, Inc. Job & Task Analysis .» 367 L. Junker - Brookhaven National Laboratory Job Performance Aids . 375 R. Moffitt - UNC Nuclear Industries, Inc. Job Analysis 379 C. Minelli - Rockwell International, Rocky Flats Plant Robotics .... , 385 W. Hamel - Oak Ridge National Laboratory Man/Machine Interface 413 R. Lindsay - Argonne National Laboratory - West Human Factors Review of DOE Facilities „ 429 R. Peterson - Lawrence Livermore National Laboratory Inservice Inspection Panel W. Scott - Idaho Chemical Processing Plant 443 R. CLouse - Union Carbide Corporation, Oak Ridge Y-12 Plant 463 Q. Baird - Hanford Engineering Development Lcjoratory 495 W. Kimble - Argonne National Laboratory - Wost 503 Thursday, March 1, 1984 DOE Headquarters and Operations Office Staff Meeting 513 Germantown, Maryland Conference Attendees 515 V TUESElAY, FEBHJARY 28, 1984 Los Alamos Safety Review Activities J. J. Koelling Los Alamos National Laboratory Los Alamos, New Mexico Los Alamos was contacted by the Office of Nuclear Materials Safety and Safeguards of the Nuclear Regulatory Commission (NRC) in 1974 to initiate an independent safety review of the proposed Plutonium Conversion Facility at the Allied General Nuclear Service's Barnwell, South Carolina, plant. Los Alamos was tasked with this effort due to the expertise they developed in the plutonium and safety fields. From 1974 until 1977 Los Alamos assisted the NRC in the safety review of nine commercial nuclear fuel plants, that were either planned or in operation. In addition, safety reviews were initiated on the NRC sponsored research reactors. During this same period, Los Alamos became involved with reviewing the physical security of all operating commercial nuclear power reactors and most research reactors. In 1978, the Department of Energy (DCE) asked Los Alamos to provide a similar independent review for their facilities. By 1984, Los Alamos had participated in the safety reviews on four DOE operated facilities. In all safety review cases, thos° systems associated with site characteri- zation, e.g., geology, hydrology, were not reviewed. Only those areas directly related to facility safety were analyzed. In addition to the '.>afety evaluations, there was often a need for review of either environmental assessments or environmental impact statements associated with operation of a facility. These reviews concentrated on essentially the same areas as in the safety reviews paying particular attention to the source terms from hypothetical accidents. 271 ABSTRACT Los Alamos Safety Review Activities Los Alamos has performed independent safety and environmental reviews or has performed evaluations in specific task areas for both the Nuclear Regulatory Commission and the Department of Energy (DOE) since initiation of the program in 1974.. During this period reviews were performed on nine commercial and four DOE operated nuclear facilities. Safety reviews were completed on fourteen research reactors. In addition, physical security reviews were performed on all operating commercial nuclear power reactors and most research reactors. 272 (8 SF3 m [Oi (3S1 ruui OIL 273 CHRONOLOGICAL DEVELOPMENT Of SAFETY REVIEWS n WB2 DOE - MEW FlR©fi Los Alamos REVIEWS PERFORCE:)-1 Review of Env ironment Q I Assessment, Bcbcock and Wllcox Park Township Site. 2 Review of Safety Evaluation Report, Babcock and Wllcox Park Township Site. 3. Review of Environmental Assessment, General Electric Vallecitos Review of Nuclear Center. 4. Review of Safety Evaluation Report, Genera! Electric Vallecitos Nuclear Center. 5. Seismic Evaluation of Building 102, General Electric Vollecitos Nuclear Center. 6. Review Summary of PSAR, E>>on Nuclear Fuel Recovery and Recycling Center. 7. Review of License Renewal Application; Environmental Report and Emergency Plan; and Comparison of Renewal Application, Battelle Colurribus Laboratory. *m REVIEWS PERFORMED-2 9. Preliminary Review of PSAR, Aerojet General Nuclear Services. 9. Preliminary Review of SAR, Nuclear Fuel Services West Valley. 10. Review of SAR and some input to EIS, Westinghouse Recycle Fuels Plani. 11. Review of Chapter IV (Environmental Impact Due io' the Implementation of Plutonium Recycle) and Chapter VII (Means for Mitigating Adverse Environmental Effects, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Rectors (GESMO)). 12. Some Planning on Decommissioning of Kerr—McGee Cimarron Plant. 13.. Review of FSAR9 Purex, Hanford *4. Preliminary Review of PSAR, Rover Fuel Reprocessing V5. Five Year Upgrade of F SAR, Savannah River Production LICENSING AMENDMENTS EVALUATED * General Atomic - Increase in the quantities ot explosives for irradiation in GA Reactor beam tubes. 3 * Union Carbide - Increase ;n allowable fission product concentration for singly encapsulated in—core thimbles. * General Electric - Ther modynami c behavior of GETR fuel in an air environment. Los Alamos NONPOWER REACTOR REVIEWS APPLICATION FOR LOS ALAMOS RENEWAL OF • REVIEW SAR BY • VISIT STTE • WRITE TER N3 00 INCORPORATES Los Alamos SAVANNAH RIVER REACTOR REVIEW DOEHQ*8 4 TECHNICAL AREAS SRP/DOE HBJD OFFICE for EENTSFED FOR Syr UPGRADE of SAR REVIEW COMPLETE REVIEW LOS ALAMOS * IOCS REVIEW DOCUMENTS and COMPLETE JOMMEMDATK ATMOSPHERIC MODEL toDOEHCTs EffyflERQENCY POWER Los Alamos "1 Safety Assessment Areas Q-6 H-1 (WX-8) H-3 CMB-11 ITO Accident Analysis X X X X Confinement X X X Ventilation & E>haust X X Process Safety X X lnstrumenta.fi on X and Control Radiation Safety X Waste Systems X X Fire & Explosion X Protection Support & Utilities \ Structural Design X and Andys is Critic a lit y Safety X X X 280 AFETY IPHYSIICAL kjRDTY KIM ©f ROJO * mPI D anxd/bfr REVIEWED flte FOLLOWING LI D) ALL OPERATING COMMERCIAL POWER Bl i) NEARLY AdJL NIONIPOWER REACTORS IB 4) FDUR DOE NUCLEAR
Load more

Recommended publications
  • Relative Fission Product Yield Determination in the Usgs
    RELATIVE FISSION PRODUCT YIELD DETERMINATION IN THE USGS TRIGA MARK I REACTOR by Michael A. Koehl © Copyright by Michael A. Koehl, 2016 All Rights Reserved A thesis submitted to the Faculty and the Board of Trustees of the Colorado School of Mines in partial fulfillment of the requirements for the degree of Doctor of Philosophy (Nuclear Engineering). Golden, Colorado Date: ____________________ Signed: ________________________ Michael A. Koehl Signed: ________________________ Dr. Jenifer C. Braley Thesis Advisor Golden, Colorado Date: ____________________ Signed: ________________________ Dr. Mark P. Jensen Professor and Director Nuclear Science and Engineering Program ii ABSTRACT Fission product yield data sets are one of the most important and fundamental compilations of basic information in the nuclear industry. This data has a wide range of applications which include nuclear fuel burnup and nonproliferation safeguards. Relative fission yields constitute a major fraction of the reported yield data and reduce the number of required absolute measurements. Radiochemical separations of fission products reduce interferences, facilitate the measurement of low level radionuclides, and are instrumental in the analysis of low-yielding symmetrical fission products. It is especially useful in the measurement of the valley nuclides and those on the extreme wings of the mass yield curve, including lanthanides, where absolute yields have high errors. This overall project was conducted in three stages: characterization of the neutron flux in irradiation positions within the U.S. Geological Survey TRIGA Mark I Reactor (GSTR), determining the mass attenuation coefficients of precipitates used in radiochemical separations, and measuring the relative fission products in the GSTR. Using the Westcott convention, the Westcott flux, ; modified spectral index, ; neutron temperature, ; and gold-based cadmium ratiosφ were determined for various sampling√⁄ positions in the USGS TRIGA Mark I reactor.
    [Show full text]
  • NRC Collection of Abbreviations
    I Nuclear Regulatory Commission c ElLc LI El LIL El, EEELIILE El ClV. El El, El1 ....... I -4 PI AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu- ments and correspondence. The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service Include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions.
    [Show full text]
  • Early Reactors from Fermi’S Water Boiler to Novel Power Prototypes
    Early Reactors From Fermi’s Water Boiler to Novel Power Prototypes by Merle E. Bunker n the urgent wartime period of the Canyon. Fuel for the reactor consumed the morning and then spend his afternoons down Manhattan Project, research equip- country’s total supply of enriched uranium at the reactor. He always analyzed the data ment was being hurriedly com- (14 percent uranium-235). To help protect as it was being collected. He was very I mandeered for Los Alamos from uni- this invaluable material, two machine-gun insistent on this point and would stop an versities and other laboratories. This equip- posts were located at the site. experiment if he did not feel that the results ment was essential for obtaining data vital to The reactor (Fig. 1) was called LOPO (for made sense.” On the day that LOPO the design of the first atomic bomb. A nuclear low power) because its power output was achieved criticality, in May 1944 after one reactor, for example, was needed for checking virtually zero. This feature simplified its final addition of enriched uranium, Fermi critical-mass calculations and for measuring design and construction and eliminated the was at the controls. fission cross sections and neutron capture and need for shielding. The liquid fuel, an LOPO served the purposes for which it scattering cross sections of various materials, aqueous solution of enriched uranyl sulfate, had been intended: determination of the particularly those under consideration as was contained in a l-foot-diameter stainless- critical mass of a simple fuel configuration moderators and reflectors.
    [Show full text]
  • DOE/EA-1410 Environmental Assessment of the Proposed
    DOE/EA-1410 Environmental Assessment of the Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico March 28, 2002 Department of Energy National Nuclear Security Administration Office of Los Alamos Site Operations EA for Disposition of the Omega West Facility TABLE OF CONTENTS EXECUTIVE SUMMARY...........................................................................................................S-1 1.0 PURPOSE AND NEED ................................................................................................... 1-1 1.1 Introduction........................................................................................................... 1-1 1.2 Background........................................................................................................... 1-2 1.3 Statement of Purpose and Need for Agency Action................................................ 1-4 1.4 Scope of This Environmental Assessment ............................................................... 1-6 1.5 Public Involvement................................................................................................. 1-6 2.0 Description of the Proposed Action and Alternatives........................................................... 2-1 2.1 History and Description of the Omega West Facility............................................... 2-1 2.1.1 History of Omega West Facility.................................................................... 2-1 2.1.2 Omega West Facility Description................................................................
    [Show full text]
  • Production Capabilities in US Nuclear Reactors for Medical Radioisotopes
    PRODUCTION CAPABILITIES IN U. S. NUCLEAR REACTORS FOR MEDICAL RADIOISOTOPES S. Mirzadeh 76 (13.3o/o) A. P. Callahan ,-o, ]_,_ R.E. Schenter ,_,,e _o,,-[ F.F. (Russ) Knapp, Jr. le_w 18ew 74 (28.6%) 69,4d 112 114 LEFT IRIDIUM 191M DISTRIBUTION OF THIS DOCUMENT IS UNLIMITE_D reportMs been reproduceddirectly from the best available copy. Available to DOE and DOE contractors from the Office of Sc_ffic end Techni- cal Information,P.O. Box 62, Oak Ridge, TN 37831; prices available from (615) 576-8401, FTS 826-8401. Available to the pub_ from the National Technical Infornmtion Service, U.S. Departmentof Commerce, 5285 Port Royal lid., Springfield,VA 22161. TNa 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, exprm or klq:4lad, or assumes any legal liability or re_oonslbilltyfor the accuracy, com- pleteness, or usefulnessof any information,apparatus, product, or process dis- closed, or rel)resem that its use would not infringe privately owned rights. Reference herein to any specific commercial product: proce_, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily consti- tute or knply its endorsement,r,mornnwndstion,or favoringby the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States L Government or any agency thereof. Cover The ORNL High Flux Reactor has the highest thermal neutron flux and is used to produce tungsten-188 which is the parent for a generator system providing carrier-free rhenium-188 for therapeutic applications.
    [Show full text]
  • Uncovered Fuel Assembly After a Loss-Of- Coolant Accident in an Mtr-Type Research Reactor
    ANL/RERTR/TM-06/01 FUEL PLATE SURFACE TEMPERATURE IN A FULLY- UNCOVERED FUEL ASSEMBLY AFTER A LOSS-OF- COOLANT ACCIDENT IN AN MTR-TYPE RESEARCH REACTOR Nuclear Science & Engineering Division About Argonne National Laboratory Argonne is a U.S. Department of Energy laboratory managed by UChicago Argonne, LLC under contract DE-AC02-06CH11357. The Laboratory’s main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov. DOCUMENT AVAILABILITY Online Access: U.S. Department of Energy (DOE) reports produced after 1991 and a growing number of pre-1991 documents are available free via DOE’s SciTech Connect (http://www.osti.gov/scitech/) Reports not in digital format may be purchased by the public from the National Technical Information Service (NTIS): U.S. Department of Commerce National Technical Information Service 5301 Shawnee Rd Alexandria, VA 22312 www.ntis.gov Phone: (800) 553-NTIS (6847) or (703) 605-6000 Fax: (703) 605-6900 Email: [email protected] Reports not in digital format are available to DOE and DOE contractors from the Office of Scientific and Technical Information (OSTI): U.S. Department of Energy Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 www.osti.gov Phone: (865) 576-8401 Fax: (865) 576-5728 Email: [email protected] Disclaimer 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 UChicago Argonne, LLC, nor any of their employees or officers, 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.
    [Show full text]
  • A Digital Controller for the Omega West Reactor
    LA--12249-MS EE92 014234 A Digital Controller for the Omega West Reactor Michael M. Minor Michael D. Kaufman Terry W. Smith* 'DOE Idaho Area Office, Idaho Falls, ID 834U2. ^rfu^fr^Csk Los Alamos National Laboratoty, CSJU U (Jvi^© Los Alamos.New Mexico 87545 Table of Contents List of Figures ix ABSTRACT xi CHAPTER 1 INTRODUCTION 1 CHAPTER 2 DESCRIPTION OF OMEGA WEST REACTOR : 2.1 Reactor Facility 3 2.2 Reactor Core 4 2.3 Reactor Control System 4 CHAPTER 3 DIGITAL CONTROL SYSTEM GUIDELINES 7 3.1 ANSI Standards 7 3.2 Technical Specifications and Operating Procedures 10 3.3 S tate of the Industry 11 CHAPTER 4 METHODS AND PROCEDURES 13 4.1 Model Control System 13 4.2 Sun Station and VME 15 4.3 Microprocessors and Xinu Operating System 18 4.4 Digital Control Modules 20 4.5 Watchdog Tuner Module 20 4.6 Signal Conditioning System 21 4.7 Stepping Motor Control System 21 4.8 Software 24 4.9 Data Acquisition and Display 30 4.10 Safety Analysis 32 4.11 Diagnostics and Troubleshooting 35 A Digital Controller for the Omega West Reactor CHAPTER 5 IMPLEMENTATION PLAN 37 5.1 Operator Training 37 5.2 Conversion to Actual System 37 CHAPTER 6 SUMMARY AND CONCLUSIONS 39 6.1 Advantages 39 6J2 Possible Improvements 39 References 41 Appendix A Controller Hardware 43 A.I Rod Drive Chassis 46 A.2 Digital Input and Display Chassis 53 A.3 Interconnections 56 A.4 ORC Drawing Index 61 Appendix B Hardware Specifications 63 B. 1 Sun-3/110 Workstation Specification 63 B.2 Model PT-VME 902A 32-Bit Repeater 64 B.3 Model VMIVME-Repeat L-45 VME Bus Long Line Repeater Link 67 B.4 MVME 105 Single Board Computer 67 B.5 VME7205 Static RAM Module 73 B.6 XVME-540 Analog I/O Module 74 B.7 XVME-240 Digital I/O Module 80 B.8 XVME-293 Counter/Timer Module 86 B.9 Model 1830 Indexer 87 B.10 Compumotor M83-135-E Stepping Motor and Optical Encoder 90 B.
    [Show full text]
  • LA-UR-17-27987 Approved for Public Release; Distribution Is Unlimited
    LA-UR-17-27987 Approved for public release; distribution is unlimited. Title: Los Alamos National Laboratory 2016 Annual Site Environmental Report Author(s): Hansen, Leslie Ann Intended for: Report Environmental Programs Issued: 2017-09-26 (rev.1) Disclaimer: Los Alamos National Laboratory, an affirmative action/equal opportunity employer, is operated by the Los Alamos National Security, LLC for the National Nuclear Security Administration of the U.S. Department of Energy under contract DE-AC52-06NA25396. By approving this article, the publisher recognizes that the U.S. Government retains nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or to allow others to do so, for U.S. Government purposes. Los Alamos National Laboratory requests that the publisher identify this article as work performed under the auspices of the U.S. Department of Energy. Los Alamos National Laboratory strongly supports academic freedom and a researcher's right to publish; as an institution, however, the Laboratory does not endorse the viewpoint of a publication or guarantee its technical correctness. Los Alamos National Laboratory ENVIRONMENTALAnnual Site REPORT Published 2017 featuring data from 2016 Annual Site Environmental Report 2016 1 Los Alamos National Laboratory Governing Policy for the Environment We are committed to act as stewards of our environment to achieve our mission in accordance with all applicable environmental requirements. We set continual improvement objectives and targets, measure and document our progress, and share our results with our workforce, sponsors, and public. Soil sampling at Los Alamos National Laboratory We reduce our environmental risk through legacy cleanup, pollution prevention, and long-term sustainability programs.
    [Show full text]
  • Technical Basis Document for the Los Alamos National Laboratory – Site Description
    ORAU Team Document Number: ORAUT-TKBS-0010-2 NIOSH Dose Reconstruction Project Effective Date: 05/07/2004 Revision No.: 00 Technical Basis Document for the Los Alamos National Controlled Copy No.: ______ Laboratory – Site Description Page 1 of 65 Subject Expert: Jack Buddenbaum Supersedes: Document Owner Approval: Signature on File Date: 04/26/2004 Jack Buddenbaum, TBD Team Leader None Approval: Signature on File Date: 04/26/2004 Judson L. Kenoyer, Task 3 Manager Concurrence: Signature on File Date: 04/27/2004 Richard E. Toohey, Project Director Approval: Signature on File Date: 05/07/2004 James W. Neton, OCAS Health Science Administrator TABLE OF CONTENTS Section Page Record of Issue/Revisions ................................................................................................................... 4 Record of Issue/Revisions ................................................................................................................... 4 Acronyms and Abbreviations ............................................................................................................... 5 2.1 Introduction ................................................................................................................................. 8 2.2 Site Activities OVERVIEW .......................................................................................................... 8 2.3 DESCRIPTIONS OF Site ACTIVITIES AND Processes ............................................................ 19 2.3.1 Plutonium and Americium ................................................................................................
    [Show full text]
  • National Environmental Policy Act Source Guide for the Hanford Site
    OL 52 HNF-SP-0903 Revision 6 National Environmental Policy Act Source Guide for the Hanford Site Date Published September 1 999 Prepared for the U.S. Department of Energy Assistant Secretary for Environment, Safety and Health RECORD COPY n.uoll DAN11L HANPOIID, INC. ~ Richland, Washington Hanford Management and Integration Contractor for the U.S. Department of Energy under Contract DE-AC06-96RL13200 ·- - Approved for Public Release; Further Dissemination Unlimited RELEASE AUTHORIZATION Document Number: HNF-SP-0903, Revision 6 National Environmental Policy Act Source Guide for the Hanford Site Document Title: September 1999 This document, reviewed in accordance with DOE Order 241 .1, "Scientific and Technical. Information Management, "and 241 .1-1, "Guide to the Management of Scientific and Technical Information," does not contain classified or sensitive unclassified information and is: APPROVED FOR PUBLIC RELEASE Lockheed Martin Services , Inc. Document Control/Information Clearance '1•--a ,or APP- 1ec"'10...,.y, ou• 1ne•• :,en11w••· ._,a1 • 111ea. <,opynanuia. upon t..0nuo11ea • .-at•nt. ,-e,1on..,,-.,yaui. nupnetarv. Prot•ct•d av.DA, Trademark. Uncl•••lfled Controlled Nuc:le&f Information. Trad• rn• rk Dl•olalmer, Ref•..,,.,• herein to •ny •pacific .:ommeriil.i produot, proc-••• of ..Nie- by trad• ~. tr•d---1<, rntnufac:turer, or otherwl•-, do.. not necu-• rily can• titut• or irntlly ltt endorMm• nt. recommendation, or fa110rina by th• Unkecl Stet.. Oo-nt or any •lllfflCY th-1 o( ltt contractor• or •ubaantrectort. Th• vl•w• end oplnlone ol authort • xpre11ad t..nln do not n• c•• Hrily •t.t• or Nnect tho" of th• United State• Govemm• nt or any agency th• reot.
    [Show full text]
  • Reaction Cross-Section at N TOF
    New experimental measurement of the 24,25,26Mg(n,) reaction cross-section at n_TOF C. Massimi on behalf of the n_TOF collaboration*) *) www.cern.ch/n_TOF EFNUDAT workshop, CERN, 30 August – 2 September Outline • Introduction and Motivation • Mg in literature • Measurement at n_TOF: Laboratory and detectors • Data analysis • Preliminary results • Conclusions Introduction Nuclear astrophysics: nucleosynthesis of elements 1. Big Bang (H, D, 3,4He, 6,7Li) 2. Nuclear fusion (A<60) 3. Neutron capture (A>60) Depending on the stellar conditions – The slow neutron-capture process (s-process): low neutron density neuton capture time longer than - decay half-lives – The rapid neutron-capture process (r-process) Introduction The s-process • is responsible for the production of about half of the elemental abundances beyond Iron that we observe today. • Most of the s-process isotopes between iron and strontium (60 < A < 90) are produced in massive stars (M > 10 – 12 Msun) where the 22Ne(,n)25Mg reaction is the main neutron source. • Beyond strontium, the s-process abundances are mostly produced in low mass Asymptotic Giant Branch stars (AGB stars, 1.2Msun<M<3Msun), The reaction path follows the where the neutrons are provided by the 13C(,n)16O reaction and by the stability valley the resulting partial activation of the abundances are determined by 22Ne(,n)25Mg reaction. the respective neutron-capture cross-section Introduction The s-process and the capture cross-section n + 25Mg cross-sections • Cross-section data is the most important nuclear physics input for s-process studies: Reaction rate = n <v> • Neutron energy: Maxwell- Boltzmann distribution Laboratory measurements are required in the energy range 0.1 < En < 300 keV.
    [Show full text]
  • NUREG-1537, Part 2 (PDF
    NUREG-1537, Part 2 Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors Standard Review Plan and Acceptance Criteria Office of Nuclear Reactor Regulation NUREG-1537, Part 2 Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors Standard Review Plan and Acceptance Criteria Manuscript Completed: February 1996 Date Published: February 1996 Office of Nuclear Reactor Regulation AVAILABILlTY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources, 1. The NRC Public Document Room, 2120 L Street, NW.. Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of docurnents cited in NRC publica- tions, i'ts not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices: licensee event reports; vendor reports and correspondence; Commission papers, and applicant and licensee docu- ments and correspondence. The following documents in the NUREG senes are available for purchase from the Govemment Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances.
    [Show full text]