RSIC Newsletter
                                    
                                    
                      Oak Ridge National Laboratory
         Post Office Box 2008 * Oak Ridge, Tennessee 37831-6362
             managed by Martin Marietta Energy Systems, Inc.
                    for the U.S. Department of Energy
                                    
                         Phone No. 615-574-6176
                            FAX 615-574-6182
              BitNet: PDC@ORNLSTC * Internet: PDC@ORNL.GOV
                                    
No. 352                                                          March 1994
    We must constantly build dikes of courage to hold back the flood
                    of fear.--Martin Luther King, Jr.
    =================================================================
                                    
    ORNL Reorganization Impacts RSIC Parent Organizational Structure
  Effective February 1, 1994, Oak Ridge
National Laboratory Director, Alvin
Trivelpiece announced the formation of a
new ORNL Directorate for Computing,
Networking, Informatics, and Education
(CNIE). The directorate includes the
following organizations: Engineering
Physics and Mathematics Division (EPMD,
RSIC's parent division), Computing
Applications Division, the Center for
Computational Sciences, the Office of
Laboratory Computing, and the Office of
Science Education Programs and External
Relations. Dr. Carl Edward Oliver is the
Associate Director of CNIE and Dr. Robert
C. Ward is the Deputy Associate Director.
Bob Ward is currently Director of the
Engineering Physics and Mathematics
Division and will act as EPMD Director
pending the announcement of his successor.
  Computational science adds a new
dimension to the more traditional
experimental and theoretical approaches to
scientific research. The use of
computational tools has become vital to most fields of science
and engineering and to many parts of the educational enterprise.
The creation of this Directorate will improve the Laboratory's
ability to advance in this area which is critical to the
Laboratory's future.

=================================================================

                     Everitt P. Blizard Scholarship

  The Executive Committee of the Radiation Protection and
Shielding Division has voted to establish a scholarship fund in
honor of Everitt P. Blizard. The scholarship is a deserving
recognition for "the father of reactor shielding," who by his
technical insight, creative visions, and personable manner,
brought the discipline of reactor shielding from an empirical art
to a respected physical science. The Everitt P. Blizard
Scholarship will be administered by the American Nuclear Society
and will be awarded annually to a graduate-level student who is
pursuing studies in the field of radiation protection and
shielding.
  WE NEED YOUR HELP. It is hoped that the endowed scholarship
can be initiated at a level of $1000, which will require that
approximately $20,000 be collected. With nearly 2000 members in
RP&S alone, a trivial contribution of only $10 each would allow
us to reach our goal. Realistically, larger individual
contributions will be needed to compensate for those who are not
able to contribute. Many employers will provide matching funds
for activities of this type, so please explore this potential for
doubling your impact. Your one-time contribution to this cause
will continue to live through the direct financial assistance to
promising young researchers and through the indirect
encouragement of new talent into our field.
  Please give this opportunity careful consideration. You may
use the enclosed form to submit your contribution. Thank you for
your generosity and your participation in this significant
activity of our division.

                                                            _Dan Ingersoll_

=================================================================

            RSIC Technical Resources Enhance User Interaction

RSIC Equipment Upgrades
To better serve the radiation transport and shielding community,
RSIC continues to acquire computer equipment and technology.
Besides having access to mainframes and supercomputers at
different sites, RSIC has acquired an IBM RISC 6000, Model 550
running AIX 3.2.5; a Sun Sparcstation 2 running Solaris 2.3; a
Sun Sparcstation 1 running SunOS 4.1.2; and an EISA-based PC-486
which is running Banyan VINES for networking. Each staff member
is equipped with a PC-486/50 and is connected to the VINES
network. All staff members have access to the Internet.

ORNL GOPHER Service
Abstracts of RSIC computer codes (CCCs and PSRs) and data
libraries (DLCs) are now available through the ORNL gopher
server. The server Internet hostname is _gopher.ornl.gov_. The
ORNL gopher internet address is _128.219.129.51_. If you have a
gopher client on your computer, you can access RSIC abstracts.
From the main menu, choose `Technical Resources'. If you have a
PC with Internet connectivity, you can obtain the Windows 3.1
gopher client software via anonymous ftp from
_lister.cc.ic.ac.uk_. Go to the directory pub/wingopher. This
Windows-based gopher software works very well in accessing the
ORNL gopher. Gopher client software for most systems is available
via anonymous ftp from _boombox.micro.umn.edu_.

Request for PC Codes on Cartridge Tapes
RSIC recently purchased a 250 Mb capacity tape drive for a PC
486. This means we will be able to address requests for PC codes
to be written on tapes. The following tapes are compatible: 
Formatted QIC-40 or Thetamat 
Formatted QIC-80 or Ximat 
Formatted DT-120 or DT-250 from Colorado Systems 
Formatted DC-2000, DC-2060, DC-2080, DC-2120 from 3M 
Formatted DC-2000, DC-2000XL, DC-2080, DC-2120 from Verbatim 
Formatted QD-2060, QD-2120 from Sony

NOTE: ONLY FORMATTED TAPES WILL BE ACCEPTED. 
NOTE: The end user tape drive must be capable of reading 250 Mb
tapes.

Request for Codes Through FTP
RSIC is moving away from distributing computer codes on 9-track
(1/2 inch) round tapes. We have occasionally responded to
requests for codes through FTP. In order to take advantage of
this service, you need to provide Dan Garner (615-574-6176, e-
mail: dlg@ornl.gov) access to your computer after the necessary
RSIC paperwork (registration, payment where applicable, etc.) has
been completed.

Media 
For UNIX-based systems, we can copy computer codes on 
4 millimeter tapes (8 gigabyte capacity compressed; 4
uncompressed) 
8 millimeter tapes (2.3 gigabyte capacity compressed; 1.2
uncompressed) 
quarter-inch data cartridge (150 megabyte capacity) 
1.44 megabyte diskettes (FOR CODES THAT WILL FIT ON ONE) 
2.0 megabyte diskettes (FOR CODES THAT WILL FIT ON ONE)

For PC-based codes, we copy on 
5.25-inch diskettes (1.2 megabytes) 
3.5-inch diskettes (1.44 megabytes) 
Bernoulli disks (90 megabytes, 150 megabytes) 
data cartridge (250 megabytes - see above)

RSIC supplies the 3.5- or 5.25-in. diskettes. For large requests
we have requested that customers send us new diskettes. The
general policy for all other tapes, cartridges, and Bernoulli
disks is for the end user to supply them. 

                                                       _Bernadette L. Kirk_

=================================================================

                 CHANGES TO THE COMPUTER CODE COLLECTION

  Six changes were made to the computer code collection. Three
new code systems were packaged and added to the collection, two
existing code packages were updated to enhance operation of the
codes, and an existing code package was replaced with a newly
frozen version. Three changes resulted from foreign
contributions.

_________________________________________________________________

CCC-200/MCNP4A
OP SYS: UNIX, DOS, VMS   
Language:   Fortran 77   
Computers: All 
Format: tar, DOS

Los Alamos National Laboratory, Los Alamos, New Mexico, has
updated this package with the addition of an install package,
which automates MCNP4A installation on nine currently supported
systems (Sun SunOS, Sun Solaris, Vax VMS, PC DOS, IBM RS/6000, HP
HPUX, DEC Ultrix, SGI IRIX, Cray UNICOS). Users who have
installed the previous release of MCNP4A do not need to request
the package but may request the first diskette on which all new
files are written. MCNP4A is a general purpose Monte Carlo code
system for calculating the time-dependent continuous-energy
transport of neutrons, photons, and/or electrons in three-
dimensional geometries.
  MCNP4A is available in UNIX tar format on cartridge tape or
on 29, 3.5-in. DS/HD (1.44 MB) diskettes in self-extracting
compressed DOS files. In addition to the source files, MCNP4A
executables are included for personal computer users. These were
created on a PC/486 under DOS 6.0 using the Lahey Fortran F77L3-
EM/32 Version 5.10 compiler. Reference: LA-12625 (1993). Fortran
77 and C; UNIX workstations, PC 386, Cray, Vax, IBM
(C00200/ALLCP/02).
_________________________________________________________________

CCC-467/ITS 3.0
OP SYS: UNIX, MVS, VMS, DOS   
Language:   Fortran 77   
Computers: Many  
Format: tar, DOS

The documentation for the ITS 3.0 code system has been updated
with the addition of a short primer written by Titan Corporation,
Albuquerque, New Mexico, to help beginning PC users get started.
Interested users who have already received the package, may
request that the primer be mailed to them. Sandia National
Laboratories, Albuquerque, New Mexico, and the National Institute
of Standards and Technology, Gaithersburg, Maryland, developed
the integrated TIGER code system, which permits a state-of-the-
art Monte Carlo solution of linear time-integrated coupled
electron/photon radiation transport problems with or without the
presence of macroscopic electric and magnetic fields of arbitrary
spatial dependence. References: SAND91-1634 (March 1992) and
informal notes. Fortran 77; Cray, IBM, Vax (C00467/MFMWS/00) or
IBM PC (C00467/PC486/01).
_________________________________________________________________

CCC-622/EXPRESS
OP SYS: UNIX, MVS-XA, VMS  
Language:   Fortran 77   
Computers: FACOM, IBM 3040, Vax 
Format: DOS

Atomic Energy Research Institute, Ibaraki-ken, Japan, through the
NEA Data Bank, Issy-les-Moulineaux, France, contributed the
emergency response supporting system EXPRESS (EXact PREparedness
Supporting System), which was developed to calculate real-time
predictions of affected areas due to radioactivities discharged
into the atmosphere from nuclear facilities. 
  The computational models in EXPRESS are the mass-consistent
wind field model (EXPRESS-I) and the particle dispersion model
(EXPRESS-II) for atmospheric dispersions. The real-time ability
of the code is obtained using a high-speed iteration method,
MILUCR (Modified Incomplete Linear Unitary Conjugate Residual),
in EXPRESS-I and a kernel density method in EXPRESS-II, which
employs a random walk model based on gradient-transfer theory.
The code was developed to run on UNIX workstations and has also
run on FACOM, IBM 3090, and Vax systems. The code package,
including sample input and output and the source files, is
transmitted on one DS/HD 5.25-in. (1.2 MB) diskette in self-
extracting compressed DOS files. Reference: JAERI-M 92-082 (June
1992). Fortran 77; FACOM, IBM 3090, Vax (C00622/MNYCP/00).
_________________________________________________________________

CCC-626/RIVER-RAD
OP SYS: DOS 
Language:   Fortran 77   
Computers: PC  
Format: DOS

Oak Ridge National Laboratory contributed the RIVER-RAD code
system for simulating the transport of radionuclides released to
rivers. The model is simplified in nature and is intended to
provide guidance in determining the potential importance of the
surface water pathway, relevant transport mechanisms, and key
radionuclides in estimating radiological dose to man. A
compartmental linear transfer model is used in RIVER-RAD. The
code system runs on IBM PC and compatible computers and has also
been tested on IBM RISC 6000 running AIX and on Vax running VMS.
The code package contains sample input and output, a PC
executable, and the RIVER-RAD source file and is transferred on
one DS/HD 3.5-in. (1.44 MB) diskette in self-extracting
compressed DOS files. Reference: ORNL/TM-12169 (November 1992.)
Fortran 77; IBM PC (C00626/MNYCP/00).
_________________________________________________________________

PSR-294/SCAT-2
OP SYS: DOS, VMS, MVS 
Language:   Fortran 77   
Computers: Many  
Format: DOS

The Centre d'Estudes de Bruyeres-le-Chatel through the NEA Data
Bank, Issy-les-Moulineaux, France, contributed a newly frozen
version of SCAT-2, which is designed as a fast, easy-to-use code
system to calculate total cross sections, elastic scattering
cross sections and their angular distributions, and transmission
coefficients from the optical model of a spherical nucleus. The
calculation is performed at a specified set of energies for one
of the following incident particles: neutron, proton, deuteron,
triton, helium-3 or alpha. SCAT-2 runs on an IBM PC/AT with a
math coprocessor using Microsoft Fortran V5.0 compiler under the
MS-DOS 3.20 operating system. It has also been tested on Vax VMS
and IBM MVS systems. One DS/HD (1.2 MB) 5.25-inch diskette
written in DOS format is used to transmit the Fortran source, PC
executable, and sample case input and output. References: CEA-N-
2227 (Oct. 1981) and NEANDC-152"A", INDC(NEA)4 (Oct. 1983).
Fortran 77; IBM PC, Vax, IBM (P00294/MNYCP/01).
_________________________________________________________________

PSR-340/LPTAU
OP SYS: DOS, VMS 
Language:   Fortran 77   
Computers: Many  
Format: DOS

Keldysh Institute of Applied Mathematics, Russian Academy of
Sciences, Moscow, through the NEA Data Bank, Issy-les-Moulineaux,
France, contributed the LPTAU, quasi-random LP(Sub)tau-sequence
generator. The sequences, uniformly distributed sets of L=M(Sup)N
points in the N-dimensional unit cube: I(Sup)N=[0,1], can be used
as nodes for multidimensional integration, as searching points in
global optimization, as trial points in multicriteria decision
making, or as quasi-random points for quasi Monte Carlo
algorithms. The number of points that can be generated is less
than 2(Sup)30. The dimension of the space cannot exceed 51. The C
and Fortran 77 versions should run on any platform with only
minor modifications where program input/output are concerned. 
The package is transmitted on one DS/HD 5.25-in. (1.2 MB)
diskette in DOS format. References: Informal documentation (1993
and 1992, _SIAM J. Numer. Anal._ Vol.16, No. 5 (October 1979).
Fortran 77 and C; IBM PC compatibles and Vax (P00340/MNYCP/00). 
=================================================================

CHANGES TO THE           DATA LIBRARY COLLECTION

  Two new data libraries were packaged and added to the
collection.

_________________________________________________________________

DLC-176/MATXS10
OP SYS: Any 
Language:   Fortran 77   
Computers: All 
Format: DOS

Los Alamos National Laboratory contributed the MATXS10 library,
with 30 neutron groups and 12 photon groups and includes 121
materials from ENDF/B-VI (including changes through Release 2).
The materials are given at 300 K without self shielding. The
weight function has a fusion + fission + 1/E + thermal Maxwellian
shape. The Legendre order for the scattering matrices is P4.
Photon production, photon interaction, KERMA, damage, and all
ENDF partial cross sections are included. Thermal upscatter is
not included.
  MATXS10 is useful for many high-energy calculations, including
coupled neutron-photon-heating calculations in fusion systems,
the analysis of fast critical assemblies like GODIVA, and some
shielding calculations for which resonance self-shielding effects
are not too important. It has the advantage of being compact, and
TRANSX2 and particle transport calculations run very fast with
this library. The current files supersede the original version of
MATXS10 included in the initial TRANSX2 release.
  BBC is included in this package to convert the library to
binary format for subsequent processing with the PSR-317/TRANSX2
code system to interface the MATXS cross-section libraries with
nuclear transport codes for radiation transport calculations. The
package is available on either 3 DS/HD 5.25-in. (1.2 MB)
diskettes in self-extracting compressed DOS files or as a
compressed tar file on cartridge tape. Reference: Informal notes
(Feb. 1994). Fortran 77; all computers (D00176/ALLCP/00).
_________________________________________________________________

DLC-177/MATXS11
OP SYS: Any 
Language:   Fortran 77   
Computers: All 
Format: tar

Los Alamos National Laboratory contributed the MATXS11 library,
with 80 neutron groups and 24 photon groups and includes 105
materials from ENDF/B-VI (including changes through Release 2).
The materials are given at up to 9 temperatures ranging from 300
to 4000 K with typically 5 to 8 background cross sections for
each temperature. The weight function has a fast reactor or
fusion blanket shape with a fusion peak at high energies and a
1/E + thermal Maxwellian extension at low energies. The Legendre
order for the scattering matrices is P5. Photon production,
photon interaction, KERMA, damage, and all ENDF partial cross
sections are included. Thermal upscatter is not included. MATXS11
is useful for most high-energy calculations, including coupled
neutron-photon-heating calculations in fusion blanket systems and
the analysis of fast reactor cores. 
  BBC is included in this package to convert the library to
binary format for subsequent processing with the PSR-317/TRANSX2
code system to interface the MATXS cross-section libraries with
nuclear transport codes for radiation transport calculations. The
package is distributed in a compressed tar file on cartridge
tape. Reference: Informal notes (Feb. 1994). Fortran 77; all
computers (D00177/ALLCP/00).
=================================================================

                             PERSONAL ITEMS

  In serving a specialized area of scientific endeavor, it seems
important that we note significant changes in the activities of
people concerned with radiation protection, transport, and
shielding in the nuclear industry. We, therefore, continue to
carry personal items as they are brought to our attention.

  Gary Lee Bennett has been elected Fellow of the American
Physical Society "for his successful management of the safety and
nuclear operations program for the radioisotope thermoelectric
generators which are now successfully operating on the Galileo
and Ulysses spacecraft."

=================================================================

                     CONFERENCES, COURSES, SYMPOSIA

  RSIC attempts to keep its users/contributors advised of
conferences, courses, and symposia in the field of radiation
protection, transport, and shielding through this section of the
newsletter. Should you be involved in the planning/organization
of such events, feel free to send your announcements and calls
for papers to RSIC.

=================================================================

                          Introduction to MCNP

The Radiation Transport Group of the Los Alamos National
Laboratory is offering an introductory class on the MCNP Monte
Carlo computer code for people who have never used MCNP or have
very limited experience. Hands-on computer sessions emphasizing
active learning will be featured. A preliminary list of session
topics follows. 

Session 1: Introduction, General Principles and Input Files
Session 2: Basic Geometry
Session 3: Advanced Geometry
Session 4: Sources
Session 5: Tallies and Statistical Analysis
Session 6: Variance Reduction
Session 7: Criticality Problems
Session 8: Physics Issues, Wrapup

  The class will be held April 5-8, 1994, at Los Alamos, New
Mexico, USA, for a cost of $1400 (U.S.). The deadline to register
is Friday, March 18, 1994. The class may be cancelled if minimum
registration is not met. For further information send e-mail to
Judi Briesmeister at jfb@lanl.gov, telephone 505-667-7277, or fax 

=================================================================

         Reactor Analysis and Radiation Transport Short Courses

  The Department of Nuclear Engineering at the University of
Tennessee-Knoxville is offering two five-day short courses of
interest to radiation transport specialists during Tennessee
Industries Week (TIW-29), August 15Minus19, 1994.
  Computational Methods in Reactor Analysis will familiarize the
course participant with computational methods and computer codes
currently used to describe the neutronic behavior of nuclear
fission reactors. Emphasis will be placed on "understanding" the
neutronic models and associated numerical methods currently
employed in codes. A good understanding of the models and methods
is essential for the successful use of the codes in designing new
reactors or improving the performance and safety of existing
reactors. Areas to be covered include multi-dimensional diffusion
theory methods and perturbation theory methods for applications
in reactor statics, space-dependent kinetics, and fuel depletion;
transport theory methods including the discrete ordinates method,
integral transport theory, and the Monte Carlo method; and cross
section generation and processing utilizing the AMPX and SCALE
systems developed at ORNL. The first day of the course will cover
the fundamentals of reactor physics beginning with the fission
process and proceeding through development of the Boltzmann
transport equation and the diffusion approximation of the
transport equation. This material will provide a good foundation
for the non-nuclear engineer for study of the more advanced
material to be presented Tuesday through Friday. For the
participant with some nuclear background, the first day would be
a review of basic nuclear engineering. 

  Monte Carlo Analysis is designed specifically for the
practicing engineer engaged in shield design and does not presume
any prior knowledge of Monte Carlo methods. However, some
understanding of radiation transport physics is desirable. A wide
range of topics will be presented that will lead to a good
understanding of the basics of Monte Carlo analysis and the
specialized applications of Monte Carlo methods to practical
shielding problems. Many advanced topics will be included that
will promote the best use of existing computer code systems.
Special attention will be paid to the understanding and Monte
Carlo implementation of the adjoint analysis. Advantages and
disadvantages of the adjoint mode versus the forward mode of
analysis will be described including several practical
applications of the adjoint mode of Monte Carlo analysis.
Variance reduction techniques will be developed in a
comprehensive fashion for both forward and adjoint calculations.
The versatile computer code system, MORSE, will be described to
illustrate the general features of Monte Carlo computer programs.
The relationships of the Monte Carlo methods to other methods of
solving radiation transport problems, such as discrete ordinates,
will be described, as well as computational advantages and
disadvantages of Monte Carlo versus the other methods. This
course will cover, in depth, the theory and mathematics a user
must have in order to understand and use the Monte Carlo method
effectively to solve difficult problems in radiation transport. 
  The registration fee is $995 per person for each course. The
deadline for registration in these two courses is July 31, 1994.
For additional information contact T. W. Kerlin, Head of the
Dept. of Nuclear Engineering, University of Tennessee, Knoxville,
TN 37996 (phone 615-974-2525).

==============================================================================

                                Calendar

  Your attention is directed to the following events of interest.

April 1994
_30th Annual Meeting of the National Council on Radiation Protection and
  Measurements_, Apr. 6-7, 1994, Arlington, Virginia. Contact: National
  Council on Radiation Protection and Measurements, 7910 Woodmont Ave., Suite
  800, Bethesda, MD 30814-3095 (phone 301-657-2652).

_Methods and Applications of Radioanalytical Chemistry (MARC III)_, Apr. 10-
  16, 1994, Kona, Hawaii, an International Topical Conference of the American
  Nuclear Society. Contact Prof. Roy H. Filby, Technical Program Chairman,
  Department of Chemistry, Washington State University, Pullman, WA 99164-
  4630 (phone 509-335-3331, fax 509-335-8867).

_Topical Meeting on Advances in Reactor Physics_, Apr. 11-15, 1994, Knoxville,
  Tennessee, sponsored by the American Nuclear Society. Contact: B. A.
  Worley, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-
  6363 USA (phone 615-574-6106).

_High Performance Computing `94: Grand Challenges in Computer Simulation_,
  Apr. 11-15, 1994, La Jolla, California, sponsored by the Society for
  Computer Simulation. Contact: Dr. Adrian Tetner, Argonne National
  Laboratory, 9700 S. Cass Ave., Argonne, IL 60439 (phone 708-252-8454).

_ARS '94, International Meeting on Advanced Reactor Safety_, Apr. 17-21, 1994,
  Pittsburgh, Pennsylvania. Contact: D. Squarer, Westinghouse Electric Corp.,
  Science and Technology Center, 1310 Beulah Road, Pittsburgh, PA 15235-5098
  USA (phone 412-256-2063; fax 412-256-1348).

_8th International Conference on Radiation Shielding_, Apr. 24-28, 1994,
  Arlington, Texas, sponsored by the American Nuclear Society with
  cooperation from several international and professional societies. Contact:
  Dr. R. M. Rubin, TU Electric, 400 N. Olive St., LB81 24 SLIC, Dallas, TX
  75201, or Nolan Hertel, Georgia Tech, Atlanta, Georgia 30332-0405 USA. R.
  W. Roussin is the International Liaison.

_RECOD '94, 4th International Conference on Nuclear Fuel Reprocessing and
  Waste Management_, Apr. 24-28, 1994, London. Contact: W. L. Wilkinson,
  RECOD '94 Steering Committee, British Nuclear Forum, 22 Buckingham Gate,
  London SW1E 6LB, United Kingdom. (phone 071-828-0116; fax 071-828-0110).

_42nd Annual Meeting of the Radiation Research Society_, Apr. 25-29, 1994,
  Nashville, Tennessee. Contact: Radiation Research Society, 1891 Preston
  White Drive, Reston, VA 22091.

_Occupational Internal Dosimetry_, Apr. 25-29, 1994, a course offered by
  REAC/TS in Oak Ridge, Tennessee. Contact: Registrar, REAC/TS, Oak Ridge
  Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-
  576-3131).

_Specialist's Meeting on Shielding Aspects of Accelerators, Targets, and
  Irradiation Facilities_, Apr. 28-29, 1994, Arlington, Texas. Contact: R. W.
  Roussin, RSIC, ORNL, P.O. Box 2008, Oak Ridge, TN 37831-6362 USA (phone
  615-574-6176; fax 615-574-6182).

May 1994
_9th Pacific Basin Nuclear Conference_, May 1-6, 1994, Sydney, Australia.
  Contact: Australian Nuclear Association, P.O. Box 445, Sutherland, NSW
  2232, Australia.

_Advanced Health Physics (C.H.P. Part 2 Exam Study)_, May 1-6, 1994. Contact:
  Woodson Assoc., Inc., P.O. Box 2665, Gaithersburg, MD 20886 (phone 301-990-
  0751, Fax 301-990-6153).

_International Workshop on Implementation of ALARA at Nuclear Power Plants_,
  May 8-11, 1994, Long Island, New York. Contact: Dr. John W. Baum or Dr. T.
  A. Khan, Brookhaven National Laboratory, ALARA Center, Upton, Long Island,
  NY 11973 USA (phone 516-282-3228, Fax 516-282-5810). 

_International Conference on Nuclear Data for Science and Technology_, May 9-
  13, 1994, Gatlinburg, Tennessee, USA. Contact: J. K. Dickens, Oak Ridge
  National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6356 USA (phone
  615-574-6115).

_Principles of Liquid Scintillation Counting_, May 11-12, 1994, a continuing
  education course presented by North Carolina State University. Contact:
  Joni M. Tanner, Office of Continuing Education and Professional
  Development, Box 7401, Raleigh, NC 27695-7401 (phone 919-515-2261, Fax 919-
  515-7614).

_1994 Symposium on Radiation Measurements and Applications_, May 16-19, 1994,
  Ann Arbor, Michigan, the 8th in a series sponsored by the U.S. Department
  of Energy. Contact: Helen Lum, Symposium Secretary, 3034 Phoenix Memorial
  Laboratory, The University of Michigan, Ann Arbor, MI 48109-2100.

_Radiation Safety Principles and Procedures_, May 16-20, 1994, a continuing
  education course presented by North Carolina State University. Contact:
  Joni M. Tanner, Office of Continuing Education and Professional
  Development, Box 7401, Raleigh, NC 27695-7401 (phone 919-515-2261, Fax 919-
  515-7614).

_Radioactive Materials Transport and Radwaste Disposal_, May 16-20, 1994.
  Contact: Woodson Assoc., Inc., P.O. Box 2665, Gaithersburg, MD 20886 (phone
  301-990-0751, Fax 301-990-6153).

_Radiopharmaceutical Internal Dosimetry_, May 16-20, 1994, a course offered by
  REAC/TS in Oak Ridge, Tennessee. Contact: Registrar, REAC/TS, Oak Ridge
  Associated Universities, P.O. Box 117, Oak Ridge, TN 37831-0117 (phone 615-
  576-3131).

_1994 International High Level Radioactive Waste Management Conference_, May
  22-26, 1994, Las Vegas, Nevada, sponsored by the American Nuclear Society
  and the American Society of Civil Engineers. Contact: William R. Wells,
  University of Nevada-Las Vegas, 4505 S. Maryland Pkwy., Las Vegas, NV
  89154-4005 (phone 702-739-3699).

June 1994
_Radiation Safety Officer Training_, June 13-17, 1994. Contact: Woodson
  Assoc., Inc., P.O. Box 2665, Gaithersburg, MD 20886 (phone 301-990-0751,
  Fax 301-990-6153).

_An Introduction to the MCBEND Monte Carlo Radiation Transport Package_, June
  14-17, 1994, a workshop presented by AEA Technology at Winfrith, U.K.
  Contact: Mrs. J. Wilkinson-James, AEA Technology, Winfrith, Dorchester,
  Dorset DT2 8DH, UK (phone 0305-202352; fax 0305-202746).

_11th Topical Meeting on the Technology of Fusion Energy_, June 19-24, 1994,
  New Orleans, sponsored by American Nuclear Society Fusion Energy Division.
  Contact: Donald J. Dudziak, Dept. of Nuclear Engineering, 110B Burlington
  Engg. Labs., North Carolina State University, Raleigh, NC 27695-7909 (phone
  919-515-2301; fax 919-515-5115, email dudziak@ncsu.edu).

_Third International Symposium on Fusion Nuclear Technology_, June 27-July 1,
  1994, University of California, Los Angeles. Contact: Dr. Mark Tillack, 44-
  139 Engineering-IV, Univ. of California, Los Angeles, CA 90024-1597 (phone
  310-206-1230; Fax 310-825-2599, Internet, MST@fusion.ucla.edu).

July 1994
_First International Congress of Environmental Geotechnics: Geotechnical and
  Related Aspects of Waste Management Associated with Municipal, Mine,
  Industrial and Nuclear Wastes_, July 10-15, 1994, Edmonton, Canada.
  Contact: D. C. Sego, University of Alberta, Dept. of Civil Engineering,
  Sego, Edmonton, TG6 2G7, Canada.

_Environmental Health Physics_, July 11-15, 1994. Contact: Woodson Assoc.,
  Inc., P.O. Box 2665, Gaithersburg, MD 20886 (phone 301-990-0751, Fax 301-
  990-6153).

_Planning for Radiation Emergencies_, July 11-15, 1994, Guildford, Surrey,
  England. Contact: Prof. J.R.A. Lakey, c/o MOS Ltd, 17 Wrotham Road,
  Gravesend, Kent DA11 OPA, UK (phone 44-0-474-350580, Fax 44-0-474-320042).

_18th International Radiation Physics Society_, July 18-22, 1994, Rabat,
  Morocco. Contact: Pr. M. Berrada, Lab. de Physique Nucleaire, Faculte des
  Sciences, B. P. 1014 Rabat, Morocco (Fax 212-7-77-99-78).

_27th International Conference on High Energy Physics_, July 21-27, 1994,
  Glasgow, United Kingdom. Contact: Institute of Physics, 47 Belgrave Square,
  London SW1X 8OX, UK.

October 1994
_European Nuclear Conference and Exhibition_, Oct. 2-6, 1994, Lyon, France.
  Contact: P. Fuez, European Nuclear Society, P.O. Box 5032, CH-3001 Berne,
  Switzerland (phone 41-31-21-61-11; fax 41-31-22-92-03).

_Meeting of the American Society for Therapeutic Radiology and Oncology_, Oct.
  3-7, 1994, Philadelphia, Pennsylvania. Contact: ASTRO, 1101 Market St.,
  14th Floor, Philadelphia, PA 19107-2990 (phone 215-574-3180).

_ANSWERS Shielding & Criticality Seminar_, Oct. 11-14, 1994, a workshop
  presented by AEA Technology at Winfrith, U.K. Contact: Mrs. J. Wilkinson-
  James, AEA Technology, Winfrith, Dorchester, Dorset DT2 8DH, UK (phone
  0305-202352; fax 0305-202746).

_Fourth Conference on Radiation Protection and Dosimetry_, Oct. 24-26, 1994,
  Orlando, Florida, sponsored by the Oak Ridge National Laboratory. Contact:
  J. S. Bogard, ORNL, P.O. Box 2008, Oak Ridge, TN 37831-6379 (phone 625-574-
  5851, fax 615-574-9174).

November 1994
_2nd Radiation Physics Conference_, Nov. 20-24, 1994, Sadaat City, Egypt,
  sponsored by the Atomic Energy Authority, Menoufia University. Contact:
  Prof. M. A. Gomaa, Atomic Energy Authority, 101. Kasr El-Aini Street,
  Cairo, Egypt (phone 02-355-8269/8264, fax 02-354-0982).

March 1995
_5th Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic
  Applications_, Mar. 26-31, 1995, Augusta, Georgia, sponsored by the ANS.
  Contact: C. E. Murphy, Westinghouse SRC, Savannah River Lab., Aiken, SC
  29808.

May 1995
_Particle Accelerator Conference_, May 1-5, 1995, Dallas, Texas. Contact:
  Richard Briggs, SSC Laboratory, 2550 Beckleymeade Avenue, Dallas, TX 75237.

==============================================================================

                    FEBRUARY ACCESSION OF LITERATURE

  The following literature cited has been ordered for review, and that
selected as suitable will be placed in the RSIC Information Storage and
Retrieval Information System (SARIS). This early announcement is made as a
service to the shielding community. Copies of the literature are not
distributed by RSIC. They may generally be obtained from the author or from a
documentation center such as the National Technical Information Service
(NTIS), Department of Commerce, Springfield, Virginia 22161. For literature
listed as available from INIS contact INIS Clearinghouse, International Atomic
Energy Agency, P.O. Box 100, A-1400 Vienna.
  _RSIC maintains a microfiche file of the literature entered into SARIS, and
duplicate copies of out-of-print reports may be available on request.
Naturally, we cannot fill requests for literature which is copyrighted (such
as books or journal articles) or whose distribution is restricted._
  This literature is on order. It is not in our system. Please order from
NTIS or other available source as indicated.

==============================================================================

                     Radiation Shielding Literature

  Health Phys. 66(2), 155-158. . _Application of the Moyer Method to
Transverse Shielding of a Linear Bremsstrahlung Source_ . . Swanson, W.P. . 
February 1994
  FEI-2104. . _Application of the Method of Partial Factorization in the
Three-Dimensional Problem of the WWER Type Reactor Neutron-Physical
Calculation_ . . Ginkin, V.P.; Troyanova, N.M. .  10/90. .  In Russian
  FEI-2324. . _The Method of Conjugate Gradients in Combination with
Incomplete Factorization and Compensation Addings in an Iterable Equation
Operator_ . . Ginkin, V.P.; Troyanova, N.M. .  10/93. .  In Russian
  UCRL-JC-114680-VGS. . _Estimated Inventory of Radionuclides in Former
Soviet Union Naval Reactors Dumped in the Kara Sea_ . . Mount, M.E.; Sheaffer,
M.K.; Abbott, D.T. .  July 1993. .  OSTI; NTIS; INIS; GPO. .  Lawrence
Livermore National Laboratory, Livermore, CA.                         EVERITT PINNELL BLIZARD
(1916-1966)

The manner in which a particular corner of science develops is
often deeply influenced by the right man appearing at the right
moment in its history. For reactor radiation shielding, that man
was Everitt Pinnell Blizard.

Everitt Blizard was born September 30, 1916, in Ottawa, Canada.
He received a bachelor's degree in chemistry from Wesleyan
University and a master's degree in physics from Columbia
University. Before completing his doctorate work, he was employed
by the Navy in 1941. As a result of his contributions in such
programs as the "CROSSROADS" atom bomb tests at Bikini, he was
selected by Captain Hyman Rickover to participate in the nuclear
submarine program and was sent to Oak Ridge, Tennessee, to attend
the charter session of a nuclear training school. Although
intended to be temporary, his stay in Oak Ridge continued until
his death from leukemia in 1966.

"Bliz," as he was better known, began with a small group of
pioneers at Oak Ridge National Laboratory and developed a
significant division of researchers addressing all aspects of
radiation shielding, including experiments, analytical models,
and nuclear data. Four major test facilities were constructed
under his leadership, beginning with the "Core Hole" facility --
a 2-ft-square hole in the shield of the original X-10 Graphite
Reactor. Although immediately successful, the facility had
significant limitations, and the group went on to develop more
powerful and more flexible test facilities, including the Lid
Tank Shielding Facility, the Bulk Shielding Facility, and the
Tower Shielding Facility. This latter facility provided the
international shielding community with abundant benchmark data
over a span of nearly four decades. Blizard also recognized the
importance of analytic methods and was instrumental in bringing
theoretical physicists together to develop and apply new methods.
His exploitation of the concept of a neutron removal cross
section had, perhaps, the widest impact on early methods
development.

Beyond Bliz's technical leadership, his humanistic interest and
sensitivity toward others often led him into a role as
international ambassador for reactor shielding. He was one of the
scientific members of the U.S. Atoms for Peace Mission to the Far
East in 1957 and participated in numerous other outreach
missions. He also contributed substantially to many handbooks and
encyclopedias, including the shielding portion of the _Reactor
Handbook _and the _Engineering Compendium on Radiation Shielding.

_Because of his vision, his technical alertness, and his warm and
inspiring personality, Blizard is rightly recognized as the
"father of reactor shielding" and is attributed with bringing the
field of reactor radiation shielding from an empirical
rule-of-thumb craft to a distinct discipline in nuclear science
and technology.