Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by UT-Battelle, LLC for the U.S. Department of Energy under contract DE-AC05-00OR22725 Phone No. 865-574-6176 FAX 865-574-6182 Internet: PDC@ORNL.GOV WWW: http://www-rsicc.ornl.gov/rsic.html
No. 432	February 2001
"With lies you may go ahead in the world...but you can never go back."  -- Russian Proverb

• NRC Codes Made Available
• CHANGE TO THE COMPUTER CODE COLLECTION
• CONFERENCES, COURSES, SYMPOSIA
• New Perspectives with Nuclear Radioactivity
• MCNP™ Workshops for the Year 2001
• PRACTICAL MCNP FOR THE HP, 
• MEDICAL PHYSICIST, AND RAD ENGINEER
• SCALE Training Course Schedule for 2001
• Calendar
• JANUARY ACCESSION OF LITERATURE
• Radiation Shielding Literature

Four U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC were incorporated into the RSICC computer software collection. Please browse the computer abstracts available at RSICC's www site for more information on these packages.

CCC-580/DPCT

CCC-630/PCDOSE

CCC-686/SWIFT2

PSR-499/GAPCON/THERMAL3

The Safety Research Institute, Kalpakkam, Tamilnadu, India, contributed a new package. GUI2QAD is an aid in preparation of input for the QAD-CGPIC program. QAD-CGPIC, which combines CCC-493/QAD-CGGP and PICTURE, is a Fortran code for neutron and gamma-ray shielding calculations by the point kernel method. Provision is available to interactively view the geometry of the system. QAD-CG calculates fast-neutron and gamma-ray penetration through various shield configurations defined by combinatorial geometry specifications. The code QAD-CGPIC is based on the point kernel method and has a provision to select either ANS-6.4.3 1990 GP buildup factor compilation or Capo's buildup factors. The code runs on Pentium-III computers under Windows operating systems. The graphical user interface is coded in Visual Basic 6 and Fortran. The executables were created with a Lahey compiler. It is transmitted on one CD. References: Informal user manual (August 2000) and CCC-493 documentation. Visual Basic 6; Fortran 77; Pentium-III (C00697PC58600).
 
 

One new data library, which was a foreign contribution, was added to the collection during the month.

The Japan Atomic Energy Research Institute, Nuclear Data Center, Tokai-mura, Japan, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed the JENDL Dosimetry File 99 (JENDL/D-99), which contains information for 47 nuclides and 67 reactions in the SAND-II group structure and as 0K preprocessed pointwise files. In addition to the present work, the sources of the reactions in this library include: JENDL-3.2, JENDL-2, EAF-99, IRDF-90V2 and others.

For the pointwise data files, the fission and capture cross sections were calculated from the resonance parameters at 0K. For the nuclides with capture and/or fission cross sections, the total cross sections, which were taken from JENDL-3.2, are provided in the pointwise form. The pointwise files include unresolved resonance parameters for self-shielding calculations, but one should not use the resonance parameters to calculate cross sections. Cross sections are given explicitly in the pointwise format (MF=3). The groupwise data were compiled by averaging cross sections in the SAND-II type energy intervals without any energy-dependent weighting function.

The package is transmitted on one CD which contains PDF documentation files and ASCII cross sections written in a self-extracting compressed DOS file. An official report on JENDL/D-99 is being prepared and will be included after it is published. References: Electronic information files (December 1999 and April 2000). ASCII card images; many computers (D00204MNYCP00).
 

Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided.
 

Location: Instituto Superior Tecnico, Lisbon, Portugal

Contact: Inquiries should be addressed to Ms. Sandra Oliveira, (tel +351-21-8419092, fax +351-21-8419143, email NRAD2001@CFIF.IST.UTL.PT).

The aim of the school is to bring together fundamental issues of nuclear radioactivity and nuclear astrophysics as well as some of the technological applications. The indicators show that sciences with a strong social impact will occupy a predominant position in the turn of the century. Nuclear physics is one of the branches of science that is expected to play an important role in this new era. On the other hand, astrophysics has always been an attraction to the human mind. Here, nuclear physics has an essential part. It is thus timely that the nuclear physics community participates actively, either addressing fundamental questions, or applying its knowledge to astrophysics and practical aspects of our society.

There will be a set of invited talks, addressing the most burning issues within the topics of the school, in a format that will allow the participant to get acquainted with some basic ideas, and simultaneously learn about the most recent developments. There will also be some invited seminars and selected short contributions.

A one-page abstract, in Latex form, is required for the selection of oral contributions. It must be sent by e-mail to NRAD2001@CFIF.IST.UTL.PT. The deadline for the submission of abstracts is June 1. The final decision will be communicated before June 30. The registration fee is 35 000 PTE. It includes coffee breaks, the welcome reception, the school banquet and a copy of the proceedings. Payment must be done on arrival. The deadline for registration is July 31. More information on the school is available on the web at: http://cfif.ist.utl.pt/~nrad2001.
 

Introductory classes are for people who have little or no experience with MCNP. The classes survey the features of MCNP so the beginning user will be exposed to the capabilities of the program, and will have hands-on experience at running the code to solve rudimentary problems. Course topics include Basic Geometry, Source Definitions, Output (Tallies) Specification and Interpretation, Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry, Tallies, and Particle Tracks, and Neutron/Photon/Electron Physics.

NOTE: While MCNP supports a number of platforms, class computers are usually Unix machines. Experience with Unix will be helpful to the student but is not essential.

Costs For Domestic U.S. Classes: Cost for the class is $1,800. There is a $300 discount if payment is received by the close of registration/early payment deadline for each class. Radiation Safety Information Computational Center (RSICC) provides the code and data package and documentation for a reduced fee of $310 to all who complete the class and free to students employed by sponsors that fund RSICC.

The class fee includes a notebook with all class viewgraphs (over 300) and handouts. Dinner the first evening is included as part of your registration fee and snacks and refreshments are provided during class breaks. Lodging will be available for roughly $75 per night. Information will be sent by follow-up letter or email when we receive your registration information.

All classes provide interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts. To register for the LANL classes via the Internet, go to http://www.solutionsbyhqc.com/mcnpform.html. For registration information on the European classes, contact Enrico Sartori, OECD/NEA at sartori@nea.fr.
 

FEE: $1,700 per person (includes the MCNP™ code package). Price subject to change without notice. Payments must be received at least 45 days before class. If payment has not been received by the due date, your space may be given up to the next available person on our waiting list. Refunds are available up to 30 days before the class date. 

PLACE: The Canyon School Complex, Los Alamos National Laboratory, Los Alamos, New Mexico.

Contacts: Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-6071, e-mail: dseagraves@lanl.gov. Technical questions may be directed to Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov. For further information and registration on the Internet, visit: http://drambuie.lanl.gov/~esh4/mcnp.htm.
 

The Los Alamos MCNP code is a general and powerful Monte Carlo transport code for photons, neutrons, and electrons. MCNP can be safely described as the "industry standard" with more than 600 person-years of development effort behind it. It is supported on a variety of platforms and is now accessible to Health Physicists, Medical Physicists, and Rad Engineers using desktop or laptop personal computers. This 4.5 day course introduces the basic concepts of Monte Carlo, demonstrates how to put together a MCNP input file, and illustrates some health and medical physics applications of the code. No prior knowledge of Monte Carlo is assumed. 

MCNP is ideally suited to the needs of professionals interested in performing radiation shielding and skyshine calculations, detector simulation studies, or dosimetry. With a little practice and study of the examples, many will find they are able to solve problems that have, in the past, been out of reach. Problems that involve a complex geometry can be easily solved using MCNP (e.g., designing a maze entrance to a radiation room). Calculations are based on detailed physics models and very accurate cross section tables that require no energy group compromises to be made. 

A copy of the MCNP code package is included in the price of the course. Your copy of MCNP will be provided directly from the Radiation Safety Information Computational Center (RSICC) at Oak Ridge. Only RSICC is authorized to distribute licensed copies of the MCNP code package. All of the input and output files for the class demonstrations will be provided for self-study on a diskette. The course will focus on providing a practical boost toward learning the program and guiding the student toward useful applications. Extensive practice sessions are scheduled using a personal computer in class. 

The course will be taught by Dick Olsher and David Seagraves of the Health Physics Measurements Group, Los Alamos National Laboratory. Additional staff help will be provided by members of the Health Physics Measurements Group. Students will be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP.
 
 

The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:

Display MCNP 4C geometries in multiple plot windows. 

Create surfaces and cells to build a geometry. 

Create materials using the local xsdir file. 

Store commonly used materials in a material library. 

Sub-divide large cells into smaller cells. 

Full geometry capabilities including universes and lattices. 

Interactively set cell importances from the plot window. 

Display source points and collision points in the plot window. 
 

A four-day class is to be held March 19-22, 2001, in Richland, Washington. The class combines teaching on MCNP physics, along with instructions on how to use the Visual Editor. Computer demonstrations and exercises will focus on creating and interrogating input files with the Visual Editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running the Linux operating system or Windows NT version if it is working by then. Since the class will provide an overview of MCNP, new users are invited to attend, however, the emphasis of the class will be on the use of the visual editor. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. For a more detailed description of the class, lodging, and course fees, please go to: http://www.pnl.gov/eshs/software/ved/class1.html.

A three-day class is to be held October 8-10, 2001, also in Richland. This class will only focus on the use of the visual editor. Users should already be familiar with the use of MCNP. Computer demonstrations and exercises will focus on creating and interrogating input files with the Visual Editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running the Linux operating system or Windows NT version if it is working by then. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on this class can be located at: http://www.pnl.gov/eshs/software/ved/class2.html.

If you have any questions concerning these classes, please contact Randy Schwarz at 509-372-4042 or email: randy.schwarz@pnl.gov.
 

Class size is limited and courses are subject to cancellation if minimum enrollment is not obtained one month prior to the course. Course fees are refundable up to one month before each class. Classes are cosponsored by RSICC. Foreign nationals must register at least six weeks in advance. For further information, contact Kay at 865-574-9213 or visit the web, http://www.cped.ornl.gov/scale/ trcourse.html.
 

SCALE Shielding and Source Terms Course (April 23-27, 2001) and (October 15-19, 2001)

The SCALE Shielding and Source Terms Course emphasizes SAS2 and ORIGEN-ARP (depletion/source-term generation) and SAS3 and SAS4 using MORSE-SGC (3-D Monte Carlo neutron/gamma shielding). It also covers SAS1/XSDRNPM (1-D neutron/gamma shielding) and QADS/QAD-CGGP (3-D point kernel gamma shielding). 
 

SCALE KENO-VI Criticality Course (April 30-May 4, 2001)

The SCALE KENO VI Criticality Course focuses on KENO VI and the associated criticality analysis sequences in CSAS6. KENO VI is the latest version of the KENO Monte Carlo criticality safety code. KENO VI contains a much larger set of geometrical bodies than KENO V.a, including cuboids, cylinders, spheres, cones, dodecahedrons, elliptical cylinders, ellipsoids, hoppers, parallelpipeds, planes, rhomboids, and wedges. The flexibility of KENO VI is increased by allowing the following features: intersecting geometry regions; hexagonal as well as cuboidal arrays; regions, holes, arrays, and units rotated to any angle and truncated to any position; and the use of an array boundary that intersects the array. Users should be aware that the added geometry features in KENO VI can result in significantly longer run times than KENO V.a. A KENO VI problem that can be modeled in KENO V.a will typically run four times as long in KENO VI as in KENO V.a. Thus the new version VI is not a replacement for the existing version V.a, but an additional version for more complex geometries that could not be modeled previously. Two-dimensional color plots of the geometry model can be generated in KENO V.a, or the model may be viewed using the KENO3D 3-D visualization tool. 
 

SCALE KENO-Va Criticality Course (October 22-26, 2001) 

The SCALE KENO V.a Criticality Course focuses on KENO V.a and the associated criticality analysis sequences in CSAS. KENO V.a is a widely used 3-D multigroup Monte Carlo criticality safety analysis code that has been in use for approximately 15 years. KENO V.a is a fast, easy-to-use code that allows users to build complex geometry models using basic geometrical bodies of cuboids, spheres, cylinders, hemispheres, and hemicylinders. Two-dimensional color plots of the geometry model can be generated. 
 

April 2001
Implications for Radiation Measurement Science, Atmospheric and Biospheric Processes, and Health Effects from Worldwide Fallout, Apr. 4-5, 2001, Arlington, VA, sponsored by the National Council on Radiation Protection and Measurements. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).

Ninth International High-Level Radioactive Waste Management Conference, Apr. 29-May 3, 2001, Las Vegas, NV, sponsored by ANS and others. Contact: Daniel Bullen, IHLRWM General Chair, (tel 515-294-6000, fax 515-294-3261, email dbullen@iaste.edu).

Radiation Transport Calculations Using the EGS Monte Carlo System, Apr. 30 - May 3, 2001, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (tel (613) 993-2715, fax (613) 952-9865, e-mail bwalters@irs.phy.nrc.ca, url www.irs.inms.nrc.ca/inms/irs/papers/egsnrc/brochure.html). 

May 2001
The ANSWERS Software Service Reactor Physics, Radiation Shielding and Nuclear Criticality Annual Seminar, May 15-17, 2001, Bournemouth, Dorset, United Kingdom, sponsored by the AEA Technology. Contact: Simon Aplin (tel + 44 (0) 1305 203634, fax +44 (0) 1305 202746, email simon.aplin@aeat.co.uk).

June 2001
ANS Annual Meeting, June 17-21, 2001, Milwaukee, WI (url www.ans.org).

September 2001
M&C 2001 Annual Meeting - Special Session: Variance Reduction for Monte Carlo Criticality Simulations, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Dr. Bojan Petrovic, (tel 412-256-1295, fax 412-256-2444, email PetrovB@westinghouse.com, url http://www.srv.net/~ians/MC2001).

November 2001
Actinides Conference, Nov. 4-9, 2001, Hayama, Japan.  Contact: Dr. T. Ogawa, Secretary for Actinides-2001 (fax +81-29-282-5922, email actq@act2001.tokai.jaeri.go.jp, web  http://act2001.tokai.jaeri.go.jp/).
 

Nucl. Sci. Eng., 137, 14-22 . . . An Adaptive Approach to Variational Nodal Diffusion Problems. . . . Zhang, H.; Lewis, E.E. . . . January 2001 . . . Northwestern University, Evanston, IL.

Nucl. Sci. Eng., 137, 23-37 . . . Composition Heterogeneity Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC) - I: Deterministic Analysis. . . . Kim, D.H.; Choi, H.; Yang, W.S.; Kim, J.K. . . . January 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea; Chosun University, Kwangju, Korea; Hanyang University, Seoul, Korea.

Nucl. Sci. Eng., 137, 38-51 . . . Composition Heterogeneity Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC) - II: Statistical Analysis. . . . Choi, H. . . . January 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Sci. Eng., 137, 52-69 . . . A Proposal for Benchmarking 235U Nuclear Data. . . . dos Santos, A.; Fuga, R.; Jerez, R.; Abe, A.Y.; Filho, E.A. . . . January 2001 . . . Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP, Sao Paulo, Brazil; Centro Technologico da Marinha em Sao Paulo - CTMSP, Sao Paulo, Brazil.

Nucl. Sci. Eng., 137, 70-88 . . . Treatment of External Levels in Neutron Resonance Fitting: Application to the Nonfissile Nuclide 52Cr. . . . Frohner, F.H.; Bouland, O. . . . January 2001 . . . Forschungszentrum Karlsruhe, Karslruhe 1, Germany; Commissariat a l'Energie Atomique, St. Paul-lez-Durance, France.

Nucl. Sci. Eng., 137, 89-95 . . . Fragment Distribution Analysis of Proton-Induced Reactions with Intermediate Energy Using Quantum Molecular Dynamics Plus Fission Models. . . . Sheng Fan; Zhu-Xiang Li; Yuheng Xiao . . . January 2001 . . . Peking University, Beijing, China; China Institute of Atomic Energy, Beijing, China; National Laboratory of Heavy Ion Accelerator, Lanzhou, China; CCAST (World Laboratory), Beijing, China; Yiyang Teachers College, Yiyang, China.

Nucl. Sci. Eng., 137, 96-106 . . . Application of Burnable Absorbers in an Accelerator-Driven System. . . . Wallenius, J.; Tucek, K.; Carlsson, J.; Gudowski, W. . . . January 2001 . . . Royal Institute of Technology, Stockholm, Sweden.

Nucl. Sci. Eng., 137, 107-110 . . . Interference of the Low-Energy Neutrons on Activation Cross-Section Measurement of the 186W(n,y)187W Reaction. . . . Guohui Zhang; Zhaomin Shi; Guoyou Tang; Jinxiang Chen; Guangzhi Liu; Hanlin Lu . . . January 2001 . . . Peking University, Beijing, China; China Institute of Atomic Energy, Beijing, China.

Nucl. Technol., 133, 1-32 . . . ATBR-A Thorium Breeder Reactor Concept for Early Induction of Thorium in an Enriched Uranium Reactor. . . . Jagannathan, V.; Pal, U.; Karthikeyan, R.; Ganesan, S.; Jain, R.P.; Kamat, S.U. . . . January 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

Nucl. Technol., 133, 33-49 . . . Kinetics of Gaseous Iodine Uptake Onto Stainless Steel During Iodine-Assisted Corrosion. . . . Wren, J.C.; Glowa, G.A. . . . January 2001 . . . Atomic Energy of Canada Limited, Chalk River, Ontario, Canada.

Nucl. Technol., 133, 50-62 . . . Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding Under Reactivity-Initiated-Accident Conditions. . . . Fuketa, T.; Sasajima, H.; Sugiyama, T. . . . January 2001 . . . Japan Atomic Energy Reseach Institute, Ibaraki-ken, Japan.

Nucl. Technol., 133, 63-76 . . . Experimental Investigation of Mixing Phenomena Inside a Concrete Containment Cooled by an Innovative Passive System. . . . Brusa, L.; Bianchi, A.; Fruttuoso, G.; Manfredini, A.; Oriolo, F.; Carelli, M.; Kendig, R.P. . . . January 2001 . . . ENEL-SGN-Rome, Italy; Universita di Pisa, Pisa, Italy; Westinghouse Sci. and Technology Center, Pittsburgh, PA.

Nucl. Technol., 133, 77-91 . . . Investigation of Core Thermohydraulics in Fast Reactors - Interwrapper Flow During Natural Circulation. . . . Kamide, H.; Hayashi, K.; Isozaki, T.; Nishimura, M. . . . January 2001 . . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

Nucl. Technol., 133, 92-102 . . . Evaluation of Impurity Behavior in the Reactor Water of a Boiling Water Reactor. . . . Igarashi, H.; Nobuyuki, O.; Usui, N.; Ohsumi, K.; Uchida, S.; Matsui, T. . . . January 2001 . . . Hitachi Engineering Company Ltd., Ibaraki, Japan; Power and Industrial Systems Research and Development Laboratory, Ibaraki, Japan; Nagoya University, Nagoya, Japan.

Nucl. Technol., 133, 103-118 . . . Removal of Zirconium in Electrometallurgical Treatment of Experimental Breeder Reactor II Spent Fuel. . . . Ahluwalia, R.K.; Hua, T.Q.; Geyer, H.K. . . . January 2001 . . . Argonne National Laboratory, Argonne, IL.

Nucl. Technol., 133, 119-132 . . . Neutron Radiography Flow Visualization of Liquid Metal Injected into an Empty Vessel and a Vessel Containing Saturated Water. . . . Sibamoto, Y.; Nakamura, H.; Anoda, Y. . . . January 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Health Phys., 80, 4-11 . . . Depth Dose-Equivalent and Effective Energies of Photoneutrons Generated by 6-18 MV X-Ray Beams for Radiotherapy. . . . d'Errico, F.; Luszik-Bhadra, M.; Nath, R.; Siebert, B.R.L.; Wolf, U. . . . January 2001 . . . Yale University School of Medicine, New Haven, CT; Physikalisch-Technische Bundesanstalt, Braunschweig, Germany; Klinik und Poliklinik fur Strahlentherapie und Radioonkologie Universitat Leipzig, Leipzig, Germany.

Health Phys., 80, 12-15 . . . Estimation of Electron Absorbed Fractions in the Extrathoracic Airways. . . . Moussa, H.M.; Eckerman, K.F.; Townsend, L.W.; Pevey, R. . . . January 2001 . . . University of Tennessee, Knoxville, TN; Oak Ridge National Laboratory, Oak Ridge, TN.

Health Phys., 80, 16-23 . . . The Measurement of Radiation Levels in Australian Zircon Milling Plants. . . . Hartley, B.M. . . . January 2001 . . . Curtin University of Technology, Bentley, Western Australia.

Health Phys., 80, 34-40 . . . A Dosimetric Model for Determining the Effectiveness of Soil Covers for Phosphogypsum Waste Piles. . . . Mas, J.L.; Bolivar, J.P.; Garcia-Tenorio, R.; Aguado, J.L.; San Miguel, E.G.; Gonzalez-Labaj . . . January 2001 . . . Universidad de Huelva, Huelva, Spain; Universidad de Sevilla, Spain.

Health Phys., 80, 47-53 . . . Monitoring Methods and Dose Assessment for Internal Exposures Involving Mixed Fission and Activation Products Containing Actinides. . . . Thind, K.S. . . . January 2001 . . . Ontario Power Generation, Ontario, Canada.

Health Phys., 80, 54-61 . . . Evaluation of Scatter Contribution from Shielding Materials Used in Scatter Measurements for Calibration Range Characterization. . . . Friedman, R.J.; Reichard, M.C.; Blue, T.E.; Brown, A.S. . . . January 2001 . . . Ohio State University, Columbus, OH.

Health Phys., 80, 62-66 . . . Absorbed Dose to the Adult Male and Female Brain from 18F-Fluorodeoxyglucose. . . . Niven, E.; Thompson, M.; Nahmias, C. . . . January 2001 . . . McMaster University Medical Center, Ontario, Canada.

Health Phys., 80, 110-125 . . . An Overview of EPA Regulation of the Safe Disposal of Transuranic Waste at the Waste Isolation Pilot Plant. . . . Wolbarst, A.B.; Forinash, E.K.; Byrum, C.O.; Peake, R.T.; Marcinowski, III, F.; Kruger, M.U. . . . February 2001 . . . U.S. Environmental Protection Agency, Washington, DC.

Health Phys., 80, 126-136 . . . Detection of Anthropogenic Radionuclides by the CA002 Monitoring Station for the Comprehensive Test Ban Treaty. . . . Measday, D.F.; Stocki, T.J.; Mason, L.R.; Williams, D.L. . . . February 2001 . . . University of British Columbia, Vancover, BC, Canada; Centre for Monitoring Research, Arlington, VA.

Health Phys., 80, 136-141 . . . Determination and Use of the Monetary Values of the Averted Person-Sievert for Use in Radiation Protection Decisions in Hungary. . . . Eged, K.; Kanyar, B.; Kis, Z.; Tatay, T.; Ivady, A.; Volent, G. . . . February 2001 . . . University of Veszprem, Hungary; Ferenc Csolnoky County Hospital, Veszprem, Hungary; Paks Nuclear Power Plant, Paks, Hungary.

Health Phys., 80, 164-169 . . . Effects of Gadolinium on the Retention and Translocation of 239Pu-Hydroxide. . . . Sato, H.; Takahashi, S.; Kubota, Y. . . . February 2001 . . . National Institute of Radiological Sciences, Chiba, Japan.

Health Phys., 80, 177-178 . . . Did NATO Attacks in Yugoslavia Cause a Detectable Environmental Effect in Hungary? . . . Kerekes, A.; Capote-Cuellar, A.; Koteles, G.J. . . . February 2001 . . . Frederic Joliot-Curie National Research Institute for Radiobiology and Radiohygiene, Budapest, Hungary.

Health Phys., 80, S7-S8 . . . Dose Rate Outside Primary Barriers. . . . McGinley, P.H. . . . February 2001 . . . Emory University School of Medicine, Atlanta, GA.

Health Phys., 80, S22-S25 . . . Minimum Detectable Activity in Gamma-Ray Spectrometry - Statistical Properties and Limits of Applicability. . . . Nir-El, Y. . . . February 2001 . . . Soreq Nuclear Research Center, Yavne, Israel.

JEFF Report 18 . . . Evaluation and Analysis of Nuclear Resonance Data . . . Frohner, F.H. . December 2000 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.