Occupational Dose Reduction at Nuclear Power Plants: Annotated Bibliography of Selected Readings in Radiation Protection andALARA
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NUREG/CR-3469
BNL-NUREG-51708
Vol.8
Occupational Dose Reduction at
Nuclear Power Plants: Annotated
Bibliography of Selected
Readings in Radiation Protection
andALARA
Manuscript Completed: April 1995
Date Published: May 1995
Prepared by
S. G. Sullivan, T. A. Khan, J. W. Xie
Brookhaven National Laboratory
Upton, NY 11973
Prepared for
Division of Regulatory Applications
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code A3259
DISTRIBUTION OF THIS DOCUMENT IS UNUMFrEDDISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, make any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.
ABSTRACT
The ALARA Center at Brookhaven National this volume. The subject index is cumulative and lists
Laboratory publishes a series of bibliographies of all abstract numbers from volumes 1 to 8. The
selected readings in radiation protection and ALARA numbers listed in boldface indicate the abstracts in this
in the continuing effort to collect and disseminate volume; the numbers not in boldface represent abstracts
information on radiation dose reduction at nuclear in previous volumes.
power plants. This is volume 8 of the series. The
abstracts in this bibliography were selected from In addition, all information in this and previous
proceedings of technical meetings and conferences, volumes of the series is available through our on-line
journals, research reports, and searches of the Energy information system called ACE (ALARA Center
Science and Technology database of the U.S. Exchange). ACE is accessible through fax machines or
Department of Energy. The subject material of these personal computers interfaced with modems. The
abstracts relates to radiation protection and dose bibliography database and other databases are kept
reduction, and ranges from the use of robotics, to current with new abstracts, information on research
operational health physics, to water chemistry. projects, and recent news of international events related
Material on the design, planning, and management of to ALARA at nuclear power plants. Access to the
nuclear power stations is included, as well as system is provided at no cost to the ALARA
information on decommissioning and safe storage community. For password certification, a manual, and
efforts. other information about our system, please contact the
ALARA Center, Building 703M, Brookhaven National
Volume 8 contains 232 abstracts, an author index, Laboratory, Upton, NY 11973, or call (516) 282-3228.
and a subject index. The author index is specific for
in NUREG/CR-3469CONTENTS
Abstract iii
Acknowledgments vii
Abstracts 1
Author Index 55
Subject Index 59
v NUREG/CR-3469ACKNOWLEDGMENTS
We would like to thank Alan K. Roecklein of the National Laboratory, for developing the software
U.S. Nuclear Regulatory Commission for his support program used to generate this report, and to Maria
and encouragement. Special thanks to Cesar Sastre of Beckman for her assistance in producing this report.
the Department of Nuclear Energy, Brookhaven
VII NUREG/CR-3469ABSTRACTS
1943. WINRE 92 - THIRD WORKSHOP ON and display of the affected zones, evaluation of the
INFORMATION MANAGEMENT IN NUCLEAR early health effects, concentration and dose rate time
SAFETY, RADIATION PROTECTION, AND dependence in the selected sites, etc. The simulation
ENVDIONMENTAL PROTECTION. Edited by of the protective measures (sheltering, iodine adminis-
HOEPFNER, K.A. (Gesellschaft Fuer Anlagen-und tration) is involved.
Reaktorsicherheit (GRS) mbH, Koeln (Germany).
WINRE-3, Koeln (Germany), 14-15 October 1992, 1945. SMALL, SIMPLE BUT USEFUL: THE
CONF-9210460, 1993 (292 p). SSI APPROACH TO A REAL-TIME SYSTEM
FOR DECISION MAKING SUPPORT.
The workshop puts much emphasis on the exchange BAEVERSTAM, U. (Swedish Radiation Protection
of experience between experts from the West and Inst., Stockholm (Sweden)). Workshop on Decision
from the Central and Eastern European countries. Making Support for Off-site Emergency Management,
The representatives from the various countries and Schloss Elmau (Germany), 25-30 October 1992,
organizations are going to introduce their respective Radiation Protection Dosimetry (United Kingdom),
data banks, products, or services. The combination of Volume 50, Number 2-4, CONF-9210458, 1993, pp.
papers and practical presentations will provide all 93-97.
with a qualified and comprehensive insight into the
tried and tested as well as the new information In case of a nuclear accident or a threat of a release,
management technologies in the specialist areas of the Swedish Radiation Protection Institute (SSI) is
nuclear safety, radiation protection, and environmental responsible for advising and informing the Govern-
protection. Furthermore, it should also contribute to ment, other authorities and the public. The institute's
the promotion of the transfer of know-how between experts are supported by a newly developed, small
experts throughout the whole of Europe. computerized system. Some components of the
system are: a simple model for atmospheric dispersion
1944. RTARC: A COMPUTER CODE FOR and dose predictions; databases including maps,
RADIOLOGICAL SEVERE ACCIDENT CONSE- nuclides, instruments and facilities to store and handle
QUENCE ASSESSMENT - MODELS AND measured values; on-line connection to nationwide
CODE DESCRD7TION. STUBNA, M.; KUSOV system of automatic measuring stations; a number of
SKA, Z. (Vyskumny Ustav Jadrovych Elektrarni, data display facilities; and computer based handbooks.
Trnava (Slovakia)). Workshop on Decision Making Most software for the system is written for the MS
Support for Off-site Emergency Management, Schloss Windows environment.
Elmau (Germany), 25-30 October 1992, Radiation
Protection Dosimetry (United Kingdom), Volume 50, 1946. NUCLEAR POWER AND THE PUBLIC.
Number 2-4, CONF-9210458, 1993, pp. 135-139. CASTELL, L. (Technische Univ. Muenchen, Garch-
ing (Germany)). Workshop on Decision Making
Real-Time Accident Release Consequence (RTARC) Support for Off-site Emergency Management, Schloss
is a computer code developed at the Nuclear Power Elmau (Germany), 25-30 October 1992, Radiation
Plants Research Institute, Trnava, Slovak Republic, to Protection Dosimetry (United Kingdom), Volume 50,
calculate and predict atmospheric transportation and Number 2-4, CONF-9210458, 1993, pp. 91-92.
off-site radiological consequences in the event of a
nuclear accident or radiological emergency during the A change in the politics of national governments
early phase. The code is used by nuclear facilities for concerning information on radiation from nuclear
basic emergency response planning and preparedness, power stations is proposed. It includes a close
real-time dose projection and dispersion calculations cooperation with those citizens' initiatives, which have
during an accident, and for post-accident analysis. established an early warning system for radioactive
The main objectives of the code are: (1) providing contamination. Today the whole population should
guidance for deploying and directing field measure- be informed in detail how to behave in case of a
ment teams; (2) evaluating the consequences of possible nuclear accident. This could avoid a likely
assumed release mechanisms and rates; (3) evaluating panic with enormous casualties in case of a major
the effectiveness of the protective measures; and (4) breakdown of a nuclear reactor in the vicinity of a
displaying data effectively in an emergency response large town. Information on the size, the equipment,
facility. The code calculations include atmospheric and the scientific standards of the initiatives are
transport and diffusion, dose assessment, evaluation given.
1 NUREG/CR-34691947. TECDO-STATUS AND RECENT DE- 1949. AVK - A DOCUMENTATION SYSTEM
VELOPMENTS. RIEDEL, U.; HOEPFNER, K.A. FOR RADIOACTIVE WASTE. GRUENDLER, D.
(Gesellschaft fuer Anlagen-und Reaktorsicherheit (Institut Fuer Sichereitstechnologie (1ST) GmbH,
(GRS) mbH, Koeln (Germany)). Workshop on Koeln (Germany)); WURTINGER, W. (Gesellschaft
Information Management in Nuclear Safety, Radiation Fuer Anlagen-und Reaktorsicherheit (GRS) mbH,
Protection and Environmental Protection (WINRE-3), Koeln (Germany)); SCHLESINGER, H. (Gesellschaft
14-15 October 1992, GRS-96, CONF-9210460, Fuer Nuklear-Service (GNS) mbH, Essen (Germany)).
January 1993, pp. 187-193 (292 p). WINRE '92 3rd Workshop on Information Manage-
ment in Nuclear Safety, Radiation Protection, and
The purpose of the closed, though company-wide Environmental Protection, 14-15 October 1992, GRS-
accessible, information retrieval system, TECDO, is 96, CONF-9210460, 1993, pp. 139-146 (292 p).
to provide central electronic storage for all technical
documents that have any importance to the safety The program AVK is a decentralized data base
evaluation of nuclear power plants and other nuclear system for bookkeeping of radioactive wastes from
facilities. This information material is made easily German nuclear power plants. It keeps track of
accessible to all installations of the GRS throughout radioactive wastes from their origin to their disposal
Germany, and also to the BMU in Bonn, through the in a final repository. AVK ensures that the exact
local and wide area networks (WAN/LAN) that location and the state of treatment of any nuclear
connect these installations. In this role as the central waste can be accurately determined at any time
information retrieval system of the GRS, TECDO required.
must provide considerable end-user friendliness such
that even the occasional user is quickly supplied with 1950. ENGINEERING AND SAFETY AS-
comprehensive information without each time requir- PECTS OF THE DECOMMISSIONING AND
ing a crash course on the how-to of PC operation. DISMANTLING OF NUCLEAR INSTALLA-
TIONS. THOMAS, W. (Gesellschaft Fuer Anlagen-
1948. OPERATION OF FINNISH NUCLEAR und Reaktorsicherheit (GRS) mbH, Garching (Ger-
POWER PLANTS. Edited by TOSSAVAINEN, K. many)). Decommissioning and Dismantling of
(Finnish Centre or Radiation and Nuclear Safety Nuclear Installations. Edited by PELZER, N., Re-
(STUK), Helsinki (Finland)), STUK-B-YTO-112, gional Meeting of the German Section of the Interna-
December 1993 (24 p). tional Nuclear Law Association: Decommissioning
and Removal of Nuclear Facilities, CONF-920755, 2-
Quarterly reports on the operation of Finnish nuclear 3 July 1992, in German, pp. 29-49 (326 p).
power plants describe events and observations related
to nuclear and radiation safety which the Finnish It is possible with the available know-how and
Centre for Radiation and Nuclear Safety considers technology to decommission even large nuclear power
safety significant. Safety-enhancing plant modifica- plants. The current decommissioning activities have
tions and general matters relating to the use of proven the suitability and feasibility of all processes
nuclear energy are also reported. A summary of the involved, which applies to scheduled decommission-
radiation safety of plant personnel and the environ- ing activities according to a licensed programme.
ment, and tabulated data on the plants' production and The experience gained so far shows: Safety of per-
their load factors are also given. At the Loviisa 1 sonnel is safeguarded. Clearing the fuel from the site
plant unit one of two specially-backed AC busbars significantly reduces the site risk or potential hazards
was lost during the second quarter of 1993. A ca. 30 to the environment, radiological protection of the
minute voltage break caused malfunctions in the plant population is safeguarded. During the period of safe
unit's electrical equipment and rendered inoperable enclosure, the collective dose to be expected reduces
certain components important to safety. The event is to approximately half the initial dose. The radioac-
rated on the International Nuclear Event Scale (INES) tive waste arisings remain practically the same. From
at level 1. In inspections carried out at TVO II the total waste volume of a nuclear power plant of
during the annual maintenance outage, the number of more than 150.000 tonnes, only about 3000 tonnes
cracks detected in control rod structural material was have to be managed as radioactive wastes. This is
higher than usual. When cracks occur, part of boron about 2% of the total material; all other wastes are
carbide, the power regulating medium in control rods, suitable for recycling. The relevant radioactivity
may wash into the reactor water and control rod measuring processes can be reliably done even in the
shutdown capability may be impaired. The event is case of large quantities of material. Decommission-
rated on the INES at level 1. Other events in the ing according to a specified programme after an
second quarter of 1993 had no bearing on nuclear or accident has happened in the facility can only be
radiation safety. done if the high-level radioactive fuel can be com-
NUREG/CR-3469pletely removed from the site. This not being feasi- the Environment of Nuclear Facility, Berlin (Ger-
ble requires the entire reactor together with the many), 24-26 October 1990, INIS-mf-14199,
radioactive inventory to be mothballed, and decom- CONF-9010555, 1991, in German, pp. 347-354
missioning work is postponed indefinitely. (461 p).
1951. IMPOSITION AND ENFORCEMENT OF Mobile ambient dose rate measuring instruments
DECOMMISSIONING REQUIREMENTS IN (radio measuring probes) shall be applied in special
THE ILK. - A PROSPECTIVE VIEW. situations, (e.g., after undue release of radioactive
GRAZEBROOK, D. (U.K. Atomic Energy Authority, material), for monitoring of the ambient dose rate in
Peaslake (United Kingdom)). Edited by PELZER, N., the environment of nuclear facilities and at other
Regional Meeting of the German Section of the places to be monitored if necessity arises, at short
International Nuclear Law Association: Decommis- notice and for short periods. They shall replace the
sioning and Dismantling of Nuclear Installations, ambient dose rate measuring rings which were in-
Schwerin (Germany), 2-3 July 1992, CONF-920755, stalled in some federal lands in accordance with the
1993, pp. 67-78 (326 p.) KFU guideline. Unlike the concept of the measuring
rings which uses measuring instruments operated
The author reviews the structure and content of permanently at every nuclear facility, the concept
existing U.K. legislation applicable to nuclear installa- described in the lecture relies on mobile measuring
tions and examines how policy decisions about instruments which are operated in response to actual
decommissioning may be accommodated therein. needs, at the place and time required. It is therefore
Planning legislation in relation to nuclear electricity not necessary to continuously operate the measuring
generating stations and other nuclear installations is instruments in the field, so that the operating costs
discussed with some reference to the proceedings at can be reduced considerably. In the Land of Lower
recent public enquiries. Environmental law governing Saxony, there are six nuclear facilities to be moni-
the keeping and dispersal of radioactive substances is tored, which at present are covered by the existing
considered. The combined effect of the Nuclear warning service measuring network, so that a number
Installations Act 1965 and the Health and Safety at of twenty radio measuring probes in the first phase
Work Act 1974 on the implementation of decommis- are considered to be sufficient.
sioning plans with particular reference to the protec-
tion of the work force and the public is summarized 1954. NUCLEAR SURVEILLANCE ON NU-
and explained. CLEAR POWER PLANTS IN POLAND. PART
2. REGULATION OF THE SECOND NUCLEAR
1952. APPLICATIONS OF ALARA CRITERIA POWER PLANT. PAWLAK, A. (National Atomic
FOR EXTERNAL WORKERS AND CONTRAC- Energy Agency, Warsaw (Poland)). Bezpieczenstwo
TORS. CAMPO, E. DEL; CASANOVA, T.; Radio- Jadrowe i Ochrona Radiologiczna (Poland), Number
protection (Spain), Volume 2, 1993, in Spanish, pp. 3, 1990, in Polish, pp. 11-14.
10-16.
The article describes licensing process of the NPP
The ICRP recommendations address for 3 sectors: "Warta" on the stage of its localization. The Nuclear
Nuclear Industry, Nuclear Medicine Facilities, and Surveillances activities focussed on such choice of the
Public in general. These recommendations focus on localization which would fulfill nuclear safety and
professional exposed workers. In another way the radiological protection requirements are discussed in
study of NRPB addresses 5 sectors: nuclear industry, detail.
health, general industry, natural radiation sources and
specialized training. This article analyzes the 1955. WESTERN AID PROGRAMS FOR
ALARA applications to contractors and external EAST EUROPEAN NUCLEAR REACTORS.
workers in Spanish Nuclear Power Plants. VAN SEUREN, J.R., (Business Unit Nuclear Energy,
Netherlands Energy Research Foundation, Petten
1953. THE USE OF MOBILE DOSE RATE (Netherlands)). Ingenieur (The Hague, Netherlands),
MEASURING STATIONS FOR EMISSION Volume 105, Number 11, November 1993, in Dutch,
MONITORING IN THE VICINITY OF NU- pp. 12-17.
CLEAR POWER PLANT. KIRCHHOFF, K.;
SALFELD, H.C. (Niederschsisches Landesamt Fuer Western organizations in the European Community
Immissionschutz, Hannover (Germany)). Eighth and of the G7 countries set up aid programs to give
Experts Meeting on Environmental Radioactivity financial and technical support to Eastern Europe to
Monitoring: Technical and Organizational Means for improve the safety of their nuclear power plants and
an Optimised Measurement of Ambient Radioactivity reactors. Attention is paid to the safety of those
NUREG/CR-3469plants, the contents of the bilateral and multilateral exposure being calculated for the reference person, as
aid programs (Technical Assistance Commonwealth required by the Radiation Protection Ordinance.
of Independent States or TACIS, and the Poland and Examples are explained.
Hungary Assistance to the Reconstruction of the
Economy or PHARE) the amount of money involved, 1958. CALIBRATION OF RADIATION MONI-
and how the programs can be carried out. TORS AT NUCLEAR POWER PLANTS. BOUD-
REAU, L. (Louisiana Laissez-Faire, Inc.,
1956. CALCULATION OF THE ANNUAL Metairie,(LA)); MILLER, A.D. (Pedro Point Technol-
RADIATION DOSE TO THE POPULATION IN ogy, Inc., Pacifica, CA); NAUGHTON, M.D.
THE VICINITY OF NUCLEAR INSTALLA- (Tarawest Technologies, San Jose, CA). Electric
TIONS DUE TO LIQUDD EFFLUENTS. GANS, Power Research Institute, Palo Alto, CA,
I. (Inst, fuer Wasser, Boden und Lufthygiene, EPRI-TR-102644, March 1994 (57 p).
Bundesgesundheitsamt, Berlin (Germany)). Eighth
Experts Meeting on Environmental Radioactivity This work was performed to provide guidance to the
Monitoring: Technical and Organizational Means for utilities in the primary and secondary calibration of
an Optimised Measurement of Ambient Radioactivity the radiation monitoring systems (RMS) installed in
in the Environment of Nuclear Facilities, Berlin nuclear power plants. These systems are installed in
(Germany), 24-26 October 1990, INIS-mf-14199, nuclear power plants to monitor ongoing processes,
CONF-9010555, 1991, in German, pp. 116-123 identify changing radiation fields, predict and limit
(461 p). personnel radiation exposures and measure and
control discharge of radioactive materials to the
Since 1974, assessments of radiation exposure due to environment. RMS are checked and calibrated on a
the emission of radioactive substances with liquid continuing basis to ensure their precision and accu-
effluents have been done by the Institut fuer Wasser-, racy. This report discusses various approaches
Boden- und Lufhygiene of the Federal Health Office towards primary and secondary calibrations of the
and data have bee published in the annual reports in RMS equipment in light of accepted practices at
the series "Umweltradioaktivitaet und Strahlenbelas- typical power plants and recent interpretations of
tung." The paper explains the radioecological models regulatory guidance. Detailed calibration techniques
of ABG and A W as far as they relate to the waste- and overall system responses, trends, and practices are
water pathway, as well as the required modifications. discussed. Industry, utility, and regulatory sources
Individual aspects of computation are explained were contacted to create an overall consensus of the
referring to the dose calculations for 1989. most reasonable approaches to optimizing the perfor-
mance of this equipment.
1957. CALCULATION OF THE ANNUAL
RADIATION DOSE TO THE POPULATION IN 1959. COMPUTER ADDED DATA PROCESS-
THE VICINITY OF NUCLEAR INSTALLA- ING FOR EXPOSURE CONTROL AT TAPS.
TIONS DUE TO ADiBORNE RADIOACTIVITY. SAWANT, R.V.; ADTANI, M.M.; SADAGOPAN,
WILDERMUTH, H.; WALTER, H.; HAUBELT, R. R.; DATTA, D. (Bhabha Atomic Research Centre,
Eighth Experts Meeting on Environmental Radioactiv- Bombay (India)). Bulletin of Radiation Protection
ity Monitoring: Technical and Organizational Means (India), Volume 14, Number 3-4, July-December
for an Optimised Measurement of Ambient Radioac- 1991, pp. 17-18.
tivity in the Environment of Nuclear Facilities, Berlin
(Germany), 24-26 October 1990, INIS-mf-14199, At TAPS 1200 radiation workers are monitored on a
CONF-9010555, 1991, in German, pp. 107-115 monthly basis. Computer-aided data processing is
(461 p). helpful to control the personnel exposures in nuclear
power plants where quickness, reliability and accu-
The annual radiation exposure of the population in racy are involved. A new algorithm DABTAP
the environment of nuclear facilities due to the (Computer Data Base Code for TAPS) was developed
emission of radioactive material is depending on for the analysis of voluminous dose data and has been
many variables and therefore can be determined only made operational on IBM PC/XT and SN-23 com-
with considerable effort. Reports therefore publish puter. Statistics reports are printed. Dose analysis is
maximum values of radiation exposure which are also done by this code which helps to keep individ-
possible, but only under the condition of simultaneous ual's dose equivalents within limits and also for
occurrence of various, unfavorable conditions. It is arranging planned exposures with selective radiation
essential in this context that the dose values are on workers quickly. The same software with little
the safe side, so that the radiation exposure is not modification can be used in other power reactors for
underestimated. This is achieved by the radiation personnel monitoring.
NUREG/CR-34691960. IMPORTANCE OF NUCLEAR POWER This chapter emphasizes the practical everyday good
PLANT TECHNOLOGY AND MANPOWER work practices in various aspects of health physics.
TRAINING. SRI RAM, K. (Indian Institute of The breadth of operational health physics is such that
Technology, Kanpur (India)). 20th Annual IARP the Chapter is organized into sections on: Section 1.
Conference on Radiation Protection, Kanpur (India), Laboratory Operation and Good Work Practices;
24-26 February 1993, Bulletin of Radiation Protection Section 2. Nuclear Power Plants; Section 3. Atmo-
(India), Volume 16, Number 1-2, CONF-9302170, spheric Dispersion and Environmental Monitoring;
January-June 1993, pp. 9-14. Section 4. Medical/Accelerator/X-Ray Diffraction;
Section 5. Emergencies. Included are pertinent data
Over the past fifty years the design of nuclear plants related to reactor source terms, atmospheric disper-
has been constantly reviewed, improved from the sion, radiation surveys, contamination guidance and
radiation exposure to public and plant integrity and release levels and surface decontamination techniques.
safety. Recently forgiving or inherently safe reactor
plant design concepts are proposed and the concept of 1963. FIRST ALARA SUCCESS AT
modular design is envisaged to cut down the delays GOLFECH. PUJOL, P. (Centre Nuclaire de Produc-
in licensing procedures and construction time. tion d'Electricite, 82 - Golfech (France)). Radiopro-
Attention is also being focused on the human factors tection (Bulletin de la Societe Francaise de Radiopro-
to avoid the type of severe accidents that have tection) (France), Volume 28, Number 4, Octo-
plagued the nuclear power plants. This paper looks ber-December 1993, in French, pp. 423-430.
at the impact of these developments on nuclear
industry and radiation protection. Since 1991, Electricite de France nuclear power
plants have started the implementation of a policy of
1961. THE NORDIC PROGRAMME FOR radiation protection optimization. At the Golfech
NUCLEAR SAFETY 1990-1993: STATUS RE- nuclear power station, one of the 20 French nuclear
PORT FOR THE FIRST HALF OF 1993. sites, an ALARA procedure was immediately set up
Nordisk Kernesikkerhedsforskning, Roskilde (Den- and the results obtained during unit 1 first outage (an
mark), NKS-93-9, August 1993 (45 p). inspection representing over 400 000 hours' work)
were most encouraging. The paper explains how -
The report contains summaries written by leaders of under the impetus of the management and ALARA
the various projects carried out under the Nordic committee - the procedure worked towards excellent
programme for nuclear safety during the first results thanks to every actors' mobilization and
half-year of 1993. The programme covers spreading motivation.
prognoses and consequences, strategy and methods
for management and exchange of data for deci- 1964. FUEL INTEGRITY AND DOSE CON-
sion-makers, the evaluation and harmonizing of TROL. GUPTA, V.K.; SUNNY, S. (Atomic Energy
countermeasures and use of intervention levels, the Regulatory Board, Bombay (India)). Annual IARP
basis for public information, Nordic emergency Conference on Radiation Protection, Kanpur (India),
exercises, the reestablishment of radioactive contami- 24-26 February 1993, Bulletin of Radiation Protection
nated areas, criteria for classification of radioactive (India), Volume 16, Number 1-2, CONF-9302170,
materials, decommissioning of uranium-cleaning January-June 1993, pp. 116-119.
plants, storage of information, removal and disposal
of contaminated soil from fields, influence of climato- Radiation exposure of personnel in nuclear power
logical and geological processes on long-term storage plants can be reduced by source control, through use
of radioactive wastes, training, quality assurance, of materials of construction which have low cobalt
aquatic radioecology, agriculture's radioecology, content and improving the integrity of fuel. Pressur-
natural and semi-natural terrestrial ecosystems, reactor ized Heavy Water Reactor design and operating
safety and personnel preparedness, safety evaluation, philosophy are ideally suited to control the fission
severe accidents and design and safety features of product inventory in the coolant by on power removal
nuclear installations in countries which are neighbors of failed fuel. A study of the radiological parameters,
to the Nordic lands. Budgets of expenditures for the collected routinely as well as through specific mea-
various project groups are presented. surements for the last eight years (1985-92) has been
analyzed. It is seen that improved fuel performance
1962. OPERATIONAL HEALTH PHYSICS. has definite effect on reducing the collective external
Edited by SHLEIEN, B. In: The Health Physics and exposure of maintenance personnel whereas it does
Radiological Health Handbook, Scinta, Inc., 1992, pp. not affect the collective exposure of operating person-
397-484 (742 p). nel. It is, therefore, necessary to investigate if the
level of exposure of operating personnel is optimal.
NUREG/CR-34691965. RADIATION-HYGIENIC PROBLEMS nuclear power. The target group of the first research
OF NUCLEAR POWER FACILITIES SHUT- was teachers in the nearby community. The subject
DOWN. NOVOZHILOV, G.N.; ZHOLUS, B.I.; of the poll was attitudes towards nuclear power and
PETROV, O.I.; GREBEN'KOV, S.V.; ALFEROV, the impact of a visit. The second research handles
A.P.; ROMANOVICH, IK. Voenno-Meditsinskii the company image of TVO target groups being local
Zhurnal (Russian Federation), Volume 3, March 1993, elected officials, press, teachers and local representa-
in Russian, pp. 41-43. tives of trade organizations. The aim of these two
studies was to measure the impact of the company's
Radiation-hygienic problems are discussed of the information and visits activities to the attitudes.
nuclear power plants (NPP) decommissioning: NPP
power units, research and test reactors, ship nuclear 1968. THE ROLE OF VISITORS CENTRES
power plants (at submarines, ice-breakers, research AT NUCLEAR FACILITY SITES. ANDERIZ
and transport ships). Attention is paid to the choice CEBRIAN, D. Nuclear Energy Agency, 75 - Paris,
of optimum variant of the NPP decommissioning. International Seminar on Visitor Centres at Nuclear
Three variants of the nuclear reactor decommissioning Facility Sites, Madrid (Spain), 2-5 November 1992,
are available: shutdown for 30-50 years with further CONF-9211298, 1993, pp. 263-272 (288 p).
total dismantling; partial dismantling with further
limited use of the NPP equipment and site for non- The Nuclear Safety Council is the agency within the
nuclear purposes; total dismantling just after the Spanish State entrusted with nuclear safety and
reactor shutdown with the use of site after the proper radiological protection. Its information activities are
treatment. Methods of the dismantling are also explained. The future creation of an information
considered. Special attention is paid to the transport- centre is being considered as part of its technical
able NPP decommissioning. Problems of the waste divulgation programme in matters of public informa-
disposal are discussed as well as radiation doses to tion.
personnel and population. Environmental impacts are
also under consideration. 1969. STRATEGDZS FOR PROMOTING
VISITS TO INFORMATION CENTRES. THE
1966. RADIATION SAFETY. INNOVATION SANTA MARIA DE GARONA EXPERIENCE.
FROM SED3ERSDORF REGISTERS RADIOAC- CORNADO, A. Nuclear Energy Agency, 75 - Paris,
TIVE HAZARD POTENTIAL. SCHMITZER,C. International Seminar on Visitor Centres at Nuclear
(Oesterrichisches Forschungszentrum Seibersdorf Facility Sites, Madrid (Spain), 2-5 November 1992,
GmbH (Austria)). Austria Innovative (Austria), CONF-9211298, 1993, pp. 239-249 (288 p).
Volume 3, October 1993, in German, pp. 15-16.
The information centre went into operation in May
The principal objective of radiation protection is to 1992. The experience accumulated over the months
maintain safety standards with respect to radiation in which the Information Centre has been in operation
exposure. Well known nuclear accidents have shown have taught all of us actively involved a lot of
that hazard potentials have to be carefully evaluated, lessons: coherence between the image of the Informa-
even without nuclear power plants on Austrian tion Centre and that of the company itself; the mes-
territory. The Austrian Research Centre has designed sage transmitted, clear and not aimed at any obvious
and developed a radiation survey meter based on an target or objective; the basic importance of the team
analysis of user requirements. This cooperation with of people as regards the attention given to the visits;
potential users and "smart solutions" in many techni- finally, attempt to establish an efficient communica-
cal areas have helped to create a device, which has tion.
found wide acceptance due to its high quality, simple
operation, and excellent performance. 1970. VISITOR CENTRE AT NUCLEAR
FACILITY SITE OF LA HAGUE.
1967. LOCAL OPINION - THE IMPACT OF MARIE-SAINTE, E.; JOZEAU-MARIGNE, M.
TWO VISITOR CENTRE STUDffiS AT OLKI- (Compagnie Generale Des Matieres Nucleaires
LUOTO. AEMMAELAE, V.M. (Teollisuuden (Cogema), Velizy-Villacoublay (France)). Nuclear
Voima Oy (Finland)). Nuclear Energy Agency, 75 - Energy Agency, 75 - Paris, International Seminar on
Paris, International Seminar on Visitor Centres at Visitor Centers at Nuclear Facility Sites, Madrid
Nuclear Facility Sites, Madrid (Spain), 2-5 November (Spain), 2-5 November 1992, CONF-9211298, 1993,
1992, CONF-9211298, 1993, pp. 273-283 (288 p). in French, pp. 159-166 (288 p).
Teollisuuden Voima Oy (TVO) has recently commis- Cogema, a french fuel reprocessing plant, reprocesses
sioned two opinion polls about attitudes towards spent fuel issued from french nuclear power plants,
NUREG/CR-3469but also Japanese, German, Swiss, Belgian, Dutch of a typical centre. The importance of regular main-
ones. Since 1976, Cogema has reprocessed more tenance and updating is emphasized.
than 5000 tons of spent fuel, about 85% of spent fuel
in the world with a market economy. Since 1976, 1973. COMPUTER VISION MAPPING SYS-
Cogema has a department which is in charge of visits TEM. CHATTERJEE, M.; UNEMORI, A;
of the firm. Five persons, communication assistants THANGAM, N.; JAIN, D. (ASD International Inc.);
in charge of relations with the public organize all HENDERSON, T. (Utah Univ., Salt Lake City, UT).
year long, visits on the site. A visitors' centre has British Nuclear Energy Society, London (United
been built in 1974 by the CEA (Commissariat a Kingdom), 2nd International Conference on Remote
FEnergie Atomique). It is opened to the public six Techniques for Nuclear Plants, Stratford-upon-Avon
months by year, from 1st of April until 30 of Septem- (United Kingdom), 10-13 May 1993, Thomas Telford
ber, seven days a week. The visitors' centre is Services Ltd, CONF-930575, 1993, pp. 348-351
situated out of the factory enclosure, so everybody (372 p).
can come in without formality. Entrance is free.
Four floors to explain what is fuel cycle, reprocess- This paper describes a system capable of accurately
ing, environment surveillance, radiation protection, mapping the pipe layout (including the associated
dosimetry, panels with elementary notions of nuclear components) in an existing nuclear power plant. The
physics (atom, fission, reactor working), use of atom system processes the images taken by a laser range
in medicine and non nuclear industry, a whole of finder and creates a 3D model of the existing pipe
general information related to nuclear historical system. Accurate mapping of the geometry, location,
record, fuel cycle, and particularly activities of La and orientation of pipe routes as well as components
Hague. will permit both the generation of the 3D CAD
database and validation of as-built plants with
1971. CHINON MUSEUM: SO AS NOT TO pre-existing CAD databases.
LOSE THE BALL. POULAIN, E. (Electricite de
France, Chinon (France)). Nuclear Energy Agency, 75 1974. LONG-TERM SAFETY OF NUCLEAR
- Paris, International Seminar on Visitor Centres at POWER PLANTS. TURNER, J., Newsletter NEA
Nuclear Facility Sites, Madrid (Spain), 2-5 November (France), Volume 11, Number 2, 1993, pp. 19-22.
1992, CONF-9211298, 1993, pp. 143-146 (288 p).
Nuclear Power Plants are getting older. How to
Of all the french nuclear power plants, Chinon is the maintain and, where possible, improve their safety
most frequented, with an average of 45,000 visitors when compared with the requirements set for modern
per year. After going through the Public Information power reactor systems, are questions that have been
Centre, visitors can see the nuclear museum (the first asked by both operators and regulators for some
commercial power plant built in France). The exhibi- years. It seems an appropriate time and it is the
tion makes it possible to more fully understand the purpose of this article to review how, at an interna-
museum and appreciate the strategy adopted to tional level, these questions are being addressed.
enhance the quality of the visits.
1975. NUCLEAR SAFETY REVIEW, 1993.
1972. CONCEPTUAL DESIGN AND EQUD?- International Atomic Energy Agency, Vienna (Aus-
MENT OF VISITOR CENTRES. HUETTINGER, tria), IAEA, STI/PUB-937, September 1993 (107 p).
K., Nuclear Energy Agency, 75 - Paris, International
Seminar on Visitor Centres at Nuclear Facility Sites, The Nuclear Safety Review 1993 describes events in
Madrid (Spain), 2-5 November 1992, the areas of radiation protection and nuclear safety
CONF-9211298, 1993, pp. 121-135 (288 p). during the previous year. Short summaries are given
of important developments in a number of individual
Discussing the needs to be met by a visitor centre, the countries together with a summary description of the
author develops the strategies to be adopted and work programmes of some international organizations
defines the items to be included in the information operating in these fields and of areas in which the
program. The procedure in preparing the layout and IAEA is involved. Discussion of three topical issues,
design are explained and the media available to as viewed by authors outside the IAEA, are also
provide various levels of information are listed. presented: the problem for the nuclear regulator of the
Principles of selecting and mixing the media are acceptability of existing nuclear power plants with
discussed and the functions of the various sections of safety deficiencies; the ongoing discussions on the
the centre described. Also included are examples of international conventions relating to legal liability
the costs and time requirements for the establishment resulting from nuclear accidents; and a detailed
7 NUREG/CR-3469review of current knowledge on the induction of monitor dose-reduction research and ALARA activi-
cancers through exposure to radiation. ties at nuclear power plants. This effort was ex-
panded in 1988 by the DOE's Office of Environment,
1976. ON NEW EVOLUTION IN DEVELOP- Safety and Health, to include DOE nuclear facilities.
MENT OF BASIC TECHNOLOGY OF ATOMIC This bibliography contains abstracts relating to
ENERGY. Atomic Energy Commission, Tokyo various aspects of ALARA program implementation
(Japan), Genshiryoku Iinkai Geppo (Journal of and dose-reduction activities, with a specific focus on
Atomic Energy Commission) (Japan), September DOE facilities. Abstracts included in this bibliogra-
1993, in Japanese, pp. 4-16. phy were selected from proceedings of technical
meetings, journals, research reports, searches of the
In 1988, the expert committee on the promotion of DOE Energy, Science and Technology Database (in
basic technology organized in the Atomic Energy general, the citation and abstract information is
Commission presented the report and showed con- presented as obtained from this database), and reprints
cretely the subjects of research and development to be of published articles provided by the authors. Facility
promoted in four fields of material technology, types and activities covered in the scope of this report
artificial intelligence technology, laser technology and include: radioactive waste, uranium enrichment, fuel
the technology for evaluating and reducing radiation fabrication, spent fuel storage and reprocessing,
risks for atomic energy, and the measures of effi- facility decommissioning, hot laboratories, tritium
ciently promoting the technical development. The production, research, test and production reactors,
research and development achieved the steady results weapons fabrication and testing, fusion, uranium and
following this report. The creation of radiation plutonium processing, radiography, and accelerators.
resistant materials, the development of knowledge Information on improved shielding design, decontami-
base system and robot technology, the development of nation, containments, robotics, source prevention and
the laser technology required for atomic energy, and control, job planning, improved operational and
the technology for evaluating and reducing radiation design techniques, as well as on other topics, has
risks and so on have been carried out. As the mea- been included. In addition, DOE/EH reports not
sures for efficiently promoting the technical develop- included in previous volumes of the bibliography are
ment, the promotion of the active interchange of in this volume (abstracts 611 to 684). This volume
researches, the intentional rearing of creative men, the (Volume 5 of the series) contains 217 abstracts.
positive development of international interchange, the
introduction of the new evaluation of research and the 1978. ALLOWANCE FOR SEVERE ACCI-
promotion of spread of the results of research have DENTS IN DESIGN. GROS, G.; CORNILLE, Y.;
been carried out. The state of execution and the new JALOUNEIX, J. (CEA Centre D'Etudes Nucleaires de
development measures of the development of the Fontenay-aux-Roses, 92 (France)). ANP '92: Interna-
basic technology are reported. tional Conference on Design and Safety of Advanced
Nuclear Power Plants, 25-29 October 1992, Compiled
1977. OCCUPATIONAL DOSE REDUCTION by OKA, Y.; KOSHIZUKA, S. (Tokyo Univ. (Ja-
AT DEPARTMENT OF ENERGY CONTRAC- pan)), Atomic Energy Society of Japan, Tokyo
TOR FACDLITffiS: BIBLIOGRAPHY OF SE- (Japan), CONF-921003, 1992, pp. 22.2/1-22.2/6
LECTED READINGS IN RADIATION PROTEC- (2182 p).
TION AND ALARA, VOLUME 5. DIONNE, B.J.;
SULLIVAN, S.G.; BAUM, J.W. (Brookhaven Na- In the paper "Safety of Future Reactors in France,"
tional Laboratory, Upton, NY). U.S. DOE Assistant the basic safety principles for future PWRs including
Secretary for Environment, Safety, and Health, the design provisions for severe accidents were
Washington, DC, DOE/EH-0364T, BNL-43228-Vol. presented. The application of the principle of defense
5, January 1994 (102 p). in depth is the central concept. The general safety
objectives for future French PWRs are summarized as
Promoting the exchange of information related to the significant reduction of the probability of core
implementation of the As Low as Reasonably Achiev- meltdown and the scale of release of radioactive
able (ALARA) philosophy is a continuing objective substance in accidents as compared to present plants
for the Department of Energy (DOE). This report and the exclusion of the excessive release to environ-
was prepared by the Brookhaven National Laboratory ment. When a probabilistic approach is used, the
(BNL) ALARA Center for the DOE Office of Health. definition of the targets to be set for these events
It contains the fifth in a series of bibliographies on which are desirable to be precluded by design provi-
dose reduction at DOE facilities. The BNL ALARA sions must be made case by case, and such design
Center was originally established in 1983 under the provisions are discussed in this paper. The investiga-
sponsorship of the Nuclear Regulatory Commission to tion of the design criteria for reactor containment and
NUREG/CR-3469other radioactivity-confining systems is based on the Paris (France), 11-13 January 1993, Organization for
identification of the relation between core meltdown Economic Co-Operation and Development,
and possible containment failure. The event se- CONF-930181, 1993, pp. 213-229 (319 p).
quences that induce both core meltdown and contain-
ment failure, or that culminate in sudden vessel Operating nuclear power plants of the most recent
failure and core meltdown, high pressure and low design feature a very low collective radiation expo-
pressure core meltdown and so on are discussed. The sure of plant personnel and very low releases of
effect of future PWR design on severe accident radioactive substances to the environment. Further
management is considered. improvements must therefore concentrate on the
elimination of design features which have become
1979. POST-IRRADIATION EXAMINATION less effective because of changes in other relevant
FACILITY FOR POWER REACTOR FUEL AT plant parameters. Future plants are likely to incorpo-
KAERI. KIM, E.-K.; LEE, K.-S.; RO, S.-G. (Korea rate additional protection against low-probability,
Atomic Energy Research Inst., Taejeon (Republic of large-consequence types of accidents. The methodol-
Korea)). Proceedings of the JAERI-KAERI Joint ogy used to verify the adequacy of such additional
Seminar on Post Irradiation Examination, Japan equipment may be similar to that used in designing
Atomic Energy Research Inst., Tokyo (Japan), 9-10 for protection against so-called design basis accidents.
November 1992, JAERI-M-93-016, CONF-9211283, However, because of their lower probability of
February 1993, pp. 17-24 (298 p). occurrence, more realistic values for the relevant
parameters should be allowed in such evaluations.
The post irradiation examination facility (PIEF) at The upper bounds which are considered to demon-
Korea Atomic Energy research Institute (KAERI) strate adequacy of protection must also be adjusted
consists of three pools, four heavy concrete cells, and for the same reason.
two lead cells. It provides adequate support services
of post irradiation examination (PIE) for nuclear 1982. A MODEL NATIONAL EMERGENCY
power reactor fuels as well as for experiments associ- RESPONSE PLAN FOR RADIOLOGICAL
ated with reactor safety studies, and fuel design and ACCIDENTS. International Atomic Energy Agency,
fabrication improvements. Capability of the PIEF Vienna (Austria), IAEA-TECDOC-718, September
includes in-pool nondestructive examination, in-cell 1993 (38 p).
nondestructive examination, metallographic examina-
tion and chemical composition analyses of irradiated The IAEA has supported several projects for the
nuclear fuels. PIE facility was put into service for development of a national response plan for radiologi-
nuclear power plant fuel from 1987. cal emergencies. As a results, the IAEA has devel-
oped a model National Emergency Response Plan for
1980. STRENGTHENING RADIATION AND Radiological Accidents (RAD PLAN), particularly for
NUCLEAR SAFETY INFRASTRUCTURES IN countries that have no nuclear power plants. This
COUNTRIES OF THE FORMER USSR. (United plan can be adapted for use by countries interested in
Nations Development Programme, International developing their own national radiological emergency
Atomic Energy Agency, Vienna (Austria)). Forum on response plan, and the IAEA will supply the latest
Strengthening Radiation and Nuclear Safety Infra- version of the RAD PLAN on computer diskette upon
structures in Countries of the Former USSR, 4-7 May request.
1993, IAEA, CONF-9305322, STI/PUB-939, Septem-
ber 1993 (143 p). 1983. FUTURE ISSUES IN RADIATION
PROTECTION: A CANADIAN PERSPECTIVE.
A Joint Secretariat of the United Nations Develop- HAYNES, M.J. (Ontario Hydro, Whitby, Ontario
ment Programme and the International Atomic Energy (Canada)). Radiation Protection on the Threshold of
Agency convened a Forum for information exchange the 21 Century, Nuclear Energy Agency, 75-Paris
of radiation and nuclear safety infrastructures of the (France), Workshop on Radiation Protection Toward
former USSR. These proceedings reflect the discus- the Turn of the Century, Paris (France), 11-13 Janu-
sions at the forum. ary 1993, Organization for Economic Co-Operation
and Development, CONF-930181, 1993, pp. 161-174
1981. RADIATION PROTECTION FOR NU- (319 p).
CLEAR POWER PLANTS WITH LIGHT WA-
TER REACTORS, STATE OF THE ART AND Radiation protection has always been a key effective-
POTENTIAL FOR IMPROVEMENTS. HOCK, R. ness area in Ontario Hydro's nuclear power program.
Nuclear Energy Agency, 75 .- Paris, Workshop on The overall collective and individual dose perfor-
Radiation Protection Toward the Turn of the Century, mance continues to be amongst the best in the world.
NUREG/CR-3469However, several important issues are emerging and dards to DRP exposures focuses radiation protection
will continue to impact the way in which the radiation resources on very low risk hazards, and is an inappro-
protection program is managed. These include priate use of the available radiation protection re-
proposed reductions in regulatory dose limits based sources.
on ICRP 60, worker and public perception of an
increased level of radiation risk, an increased pres- 1985. ACHIEVEMENTS OF RADIATION
ence of organised labour in the formulation of radia- PROTECTION IN NUCLEAR POWER - KEY
tion protection policy, our philosophy of self protec- FACTORS RELEVANT FOR DOSE REDUC-
tion coming under challenge and the impact of TION. PFEFFER, W. (Gesellschaft Fuer Reak-
heavily audited radiation protection practices and torsicherheit Mbh (GRS), Koeln (Germany)). Radia-
programs. Each of these issues will be discussed tion Protection on the Threshold of the 21 Century,
further in this paper. The Ontario Hydro ALARA Nuclear Energy Agency, Paris (France), Workshop on
program is briefly covered although it is considered Radiation Protection Toward the Turn of the Century,
not to be a future issue but rather a principle which Paris (France), 11-13 January 1993, Organization for
has been incorporated into the design and operation Economic Co-Operation and Development,
of our stations for many years. CONF-930181, 1993, pp. 69-97 (319 p).
1984. NONSTOCHASTIC SKIN EFFECTS Many efforts have been taken to reduce the radiologi-
FROM DISCRETE RADIOACTIVE PARTICLES cal exposure of the public and of the personnel which
EMITTING HIGH-ENERGY SPECTRA BETA is caused by the production of nuclear power. Key
RAYS. REECE, W.D. (Texas A & M University, factors contributing to the dose reduction are ad-
College Station, TX); DURHAM, J.S.; MERWIN, dressed in the paper ranging from design of the plant,
S.E.; MOELLER, M.P. (Battelle Pacific Northwest operating experience, work management and training
Laboratory, Richland, WA); OWEN, D.E. (ENCORE of the personnel to reduction techniques implemented
Technical Resources, Inc., Middletown, PA). Electric to reduce the releases of the plants. Some data are
Power Research Inst., Palo Alto, CA, presented to point out the improvements gained and
EPRI-TR-102658, October 1993 (63 p). to show the effect of certain factors. Improvements
to be aimed at in the future regarding harmonization
Among the more contentious radiation protection and information transfer in an international frame are
issues in recent years has been the debate over the addressed.
risk to nuclear power plant workers from beta radia-
tion-emitting discrete radioactive particles (or DRPs). 1986. HIGH ENERGY PHOTON RESPONSE
DRPs — sometimes called "hot particles" are small, OF DIFFERENT ENVIRONMENTAL TLDs.
usually microscopic, radioactive particles that can SAEZ-VERGARA, J.C.; GOMEX-ROS, J.M.; DEL-
adhere to the skin and protective clothing of plant GADO, A. (Centro De Investigaciones Energeticas,
workers and potentially produce high radiation doses Medioambientales y Technologicas (CIEMAT),
to very small areas of the skin. In response to Madrid (SPAIN)). 10th International Conference on
regulations that don't account for DRPs, nuclear Solid State Dosimetry, 13-17 July 1992, Radiation
power plants are expending considerable financial and Protection Dosimetry (United Kingdom), Volume 47,
personnel resources to monitor workers for DRPs and Number 1-4, CONF-920702, 1993, pp. 327-330.
to prevent the spread of DRPs within the plant. In
the process, power plant workers are incurring addi- The presence of high energy photons (4-7 Me) around
tional whole body radiation exposure. Concern over nuclear power plants and high energy accelerators is
DRP exposures is based on the knowledge that important during operation. Environmental monitor-
various types of nonstochastic skin injuries can result ing frequently uses passive TL measurements for the
from sufficiently high beta radiation doses. While the assessment of the radiological impact of these facili-
effects for large-area irradiations (several square ties. However, due to the presence of this energetic
centimeters and larger) are generally well understood, photon radiation component, the design of environ-
the effects for doses to very small areas are less clear. mental TLDs must be reconsidered, in order to
The evidence, however, is clear that biological injury provide charged particle equilibrium. The energy
dose thresholds for DRP irradiations are much larger dependence of phosphors (LiF:Mg,Ti, Li B 0 :Cu,
2 4 7
than the dose limits prescribed in existing regulations CaS0 :Tm) in different irradiation conditions has
4
for large-area skin exposures. One concern is that been measured in the range 0.6-6.5 Me. Irradiations
nuclear power plant efforts to comply with the current using 6 Me photons were performed in the calibration
skin protection standard causes workers to receive facility recently established at PTB (Gennany). These
unnecessary whole-body radiation exposure. In data also seem to indicate that it could be necessary
addition, applying the existing skin protection stan- to apply specific corrections to the TLD readouts to
NUREG/CR-3469account for these high energies and the convenience Spanish Electricity Sector in the international nuclear
of the use of a discriminant TL dosemeter with scene.
special dose calculation algorithms for this radiation.
These algorithms are usually based on element ratios 1989. THE PRESENCE IN THE PROGRAMS
and can be impractical in field readouts. However, FOR IMPROVING NUCLEAR SAFETY IN THE
this is not a serious limitation since the maximum EASTERN EUROPEAN COUNTRIES. GONZA-
error should not exceed ±10%. LEZ DE UBIERTA, A., Revista de la Sociedad
Nuclear Espanola (Spain), Volume 126, 1993, pp.
1987. D E V E L O P M E N T OF A 35-37.
GENERAL-PURPOSE MOBILE ROBOT FOR
USE IN NUCLEAR POWER PLANTS. MARTI- The program of the improvement of nuclear safety in
NEZ, A.; YAGUE, M.A.; LINARES, F., Revista de Eastern Europe offers both the Electricity Sector and
la Sociedad Nuclear Espanola (Spain), Volume 295, the Spanish Nuclear Industry an opportunity to apply
1993, pp. 47-51. their wide technological capabilities and to contribute
to strengthening of the nuclear option, which is
In recent years, the Space Division of Construcciones perceived as being of fundamental importance to
Aeronauticas (CASA) and Equipos Nucleares (ENSA) ensure the supply of electrical energy that will be
have participated in several national and international demanded by the industrialized societies in the
robotics programs in the respective space and nuclear medium and log term.
areas. In mid-1992, they decided to jointly undertake
the development of a mobile inspection and mainte- 1990. PREPARING FOR THE NEXT CHER-
nance robot for Nuclear Power Plants. The success NOBYL. COUGHLAN, S., IEE Review (United
of such a multidisciplinary project was ensured by the Kingdom), Volume 39, Number 5, 16 September
way both companies complement each other and by 1993, pp. 207-210.
their previous development. Work was begun on the
feasibility study and specifications, for which techni- Some fifty-six nuclear power plants in eastern Europe
cal meetings were held with personnel from the and the former Soviet Union are, by western stan-
Medical and Health Physics Association of the dards, in a dangerous condition. Although a pro-
utilities (AMYS) and several Nuclear Power Plants. gramme of refurbishment and decommissioning is
The result of these conversations was a preliminary underway this is a long-term task. In the meantime
system design along with the specifications with it is hoped to set up an early warning system of
which the system must comply. With these results, a nuclear incidents for Eastern Europe and the west.
report and job plan were prepared for construction of Under the European Commission programme of
two prototypes and submitted to the INI (National technical assistance to the CIS, a feasibility study has
Institute of Industry Shareholder of both CASA and been carried out for a radiation incident monitoring
ENSA), which decided to finance this second Phase system for Ukraine and Belarus. This could provide
of Development by charging it to the Group's Re- early warning of the likelihood of radioactive fallout.
search Development Fund. The study was to provide a costed, phased, high-level
design for a monitoring system. The results are
1988. UNESA PARTICIPATION EST INTERNA- summarized. A full technical design of a pilot system
TIONAL R & D PROJECTS IN THE FIELD OF is now underway.
NUCLEAR SAFETY. PUGA, J., Revista de la
Sociedad Nuclear Espanola (Spain), Volume 126, 1991. CONTROL OF NUCLEAR FUEL AND
1993, pp. 39-41. OTHER MATERIALS REQUDJED IN THE
OPERATION OF NUCLEAR POWER PLANTS.
The participation of the Spanish Electricity Sector, in Finnish Centre for Radiation and Nuclear Safety
the framework of UNESA, in international efforts to (STUK), Helsinki (Finland), STUK/YVL-GUIDE-6.1,
carry out nuclear safety research projects has been 1993 (12 p).
successful for the fulfillment of the original objec-
tives. The direct involvement in the development of The control of nuclear fuel and other nuclear materi-
the work of technical staff from the utilities and the als in Finland is based on the Finnish nuclear energy
nuclear power plants has proven to be an efficient and radiation protection legislation, regulations and
way to transfer technology and valuable results to the the decisions of the Council of State as well as
final users. UNESA looks forward to continuing this Finland's international treaties concerning nuclear
way of participation in R&D projects in the nuclear energy field. The regulatory authority of the control
safety area as part of the general involvement of the is the Finnish Centre for Radiation and Nuclear
Safety (STUK). The guide summarizes the general
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