Filters
Results 1 - 10 of 60
Results 1 - 10 of 60.
Search took: 0.023 seconds
Sort by: date | relevance |
AbstractAbstract
[en] This paper briefly describes the Health Physics and ALARA programs, practices and experience at Duke Power Company, particularly at the Oconee Nuclear Station. It consists of three PWR units and has been operating for more than 10 years now. In the beginning, the Corporate System Health Physics staff established the Health Physics Program and later the ALARA Program for the station and an independent station Health Physics organization has conducted the program. The corporate Health Physics organization also provides technical guidance and direction to the station in conducting the program and reviews its effectiveness, modifying it as necessary based on experience and new regulations
Primary Subject
Secondary Subject
Source
Anon; vp; 1985; p. 1-2; American Nuclear Society; La Grange Park, IL (USA); ANS executive conference on dollars and sense in good radiation protection management; San Diego, CA (USA); 9-12 Dec 1984; CONF-841223--
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Office of Radiation Programs, Washington, D.C. (USA). Surveillance and Inspection Div; p. 131-160; Sep 1972; Southern conference on environmental protection from nuclear power plants; St. Petersburg, FL; 2 Apr 1971
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ATMOSPHERIC PRECIPITATIONS, ANIMALS, DUSTS, EARTH ATMOSPHERE, ENVIRONMENT, FISHES, GASEOUS WASTES, LIQUID WASTES, MAXIMUM PERMISSIBLE DOSE, MC GUIRE-1 REACTOR, MC GUIRE-2 REACTOR, MILK, NORTH CAROLINA, NUCLEAR POWER PLANTS, OCONEE-1 REACTOR, OCONEE-2 REACTOR, PLANTS, RADIATION DOSES, RADIATION MONITORING, RADIATION PROTECTION, RADIOACTIVE WASTES, RADIOACTIVITY, RAIN, SAMPLING, SOILS, SOUTH CAROLINA, SURFACE WATERS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Our visions of the future are often very optimistic and hopeful, representing the best imaginings of the human mind. The authors are inclined to think of the future as filled with new and better things. Some people even visualize the future as a science fiction perfection, but, in reality, it will also contain elements of the past and the present, both good and bad. With respect to radiation protection, a guess would tell us that the future holds the implementation of some version of ICRP-26 in one revision or another of the NRC 10 CFR20 regulations. But many of the technical problems of today may likely be ''solved'' by the public, the politicians, the sociologists and the bureaucrats of the future. For example, two such ''solutions'' may possibly appear in such grotesque forms as drastically lowered allowable annual doses or as engineered facilities for the disposal of low-level radioactive waste above ground on seismic stilts. All of these aspects - the good, the bad, the new, the old, and the indifferent - are all touched upon in this vision of the future
Primary Subject
Secondary Subject
Source
Anon; p. 291-294; ISBN 0-89448-132-0; ; 1987; p. 291-294; American Nuclear Society; La Grange Park, IL (USA); Topical conference on theory and practice in radiation protection and shielding; Knoxville, TN (USA); 22-24 Apr 1987
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Commander, J.C.; Lewis, L.; Hammer, R.
Aerojet Nuclear Co., Idaho Falls, Idaho (USA). Idaho National Engineering Lab1975
Aerojet Nuclear Co., Idaho Falls, Idaho (USA). Idaho National Engineering Lab1975
AbstractAbstract
[en] Decontamination and decommissioning of the Experimental Breeder Reactor No. 1 (EBR-I) requires processing of the primary coolant, an eutectic solution of sodium and potassium (NaK), remaining in the EBR-I primary and secondary coolant systems. While developing design criteria for the NaK processing system, reasonable justification was provided for the development of a pilot test plant for field testing some of the process concepts and proposed hardware. The objective of this activity was to prove the process concept on a low-cost, small-scale test bed. The pilot test plant criteria provided a general description of the test including: the purpose, location, description of test equipment available, waste disposal requirements, and a flow diagram and conceptual equipment layout. The pilot plant test operations procedure provided a detailed step-by-step procedure for operation of the pilot plant to obtain the desired test data and operational experience. It also spelled out the safety precautions to be used by operating personnel, including the requirement for alkali metals training certification, use of protective clothing, availability of fire protection equipment, and caustic handling procedures. The pilot plant test was performed on May 16, 1974. During the test, 32.5 gallons or 240 lb of NaK was successfully converted to caustic by reaction with water in a caustic solution. (auth)
Primary Subject
Source
Jun 1975; 24 p
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Source
Meeting of the American Nuclear Society; Washington, District of Columbia, USA; 27 Oct 1974; See CONF-741017-- Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Trans. Amer. Nucl. Soc; v. 19 p. 448-449
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 24 p. 485-486
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
American Nuclear Society's annual meeting; Miami Beach, FL (USA); 7 - 12 Jun 1981; CONF-810606--; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; ISSN 0003-018X; ; v. 38 p. 591-592
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lewis, L.; Ostrow, S.L.
Proceedings of the international nuclear reactor decommissioning planning conference1985
Proceedings of the international nuclear reactor decommissioning planning conference1985
AbstractAbstract
[en] Intact decommissioning of nuclear power plants is a technically viable alternative to the other decommissioning options. It appears possible, with a high degree of confidence, to establish boundaries that would remain impregnable and therefore prevent the escape of residual radioactivity for at least 100 years (based on very conservative assumptions) following the active phase of decommissioning. By that time, most of the radionuclides would have decayed to insignificant levels leaving, primarily, activity from a few radionuclides remaining in the activated reactor vessel stainless steel internals. Following a postulated breach of the boundary at 100 years, potential public exposures estimated out to 10,000 years would be within regulatory limits, and comparable to those for the other decommissioning scenarios. This study considers a 660 Mw(e) Mark I containment BWR, and a 1,175 MW(e) PWR located in generic environments with characteristics similar to the northeastern and midwestern parts of the United States, respectively. The primary containment boundaries are established as the intact decommissioning boundaries for both plants, and occupational and public doses are calculated
Primary Subject
Secondary Subject
Source
Baumann, B.L.; Edwards, K.M; p. 487-490; 1985; p. 487-490; Government Printing Office; Washington, DC (USA); International nuclear reactor decommissioning planning conference; Bethesda, MD (USA); 16-18 Jul 1985
Record Type
Book
Literature Type
Conference
Country of publication
BWR TYPE REACTORS, CONTAINMENT, CONTAINMENT BUILDINGS, CONTAINMENT SHELLS, CONTAMINATION REGULATIONS, DOSE LIMITS, HUMAN POPULATIONS, LAW, MAXIMUM PERMISSIBLE EXPOSURE, NUCLEAR ENGINEERING, NUCLEAR POWER PLANTS, PERSONNEL, PWR TYPE REACTORS, RADIATION DOSES, RADIATION PROTECTION, RADIONUCLIDE MIGRATION, REACTOR DECOMMISSIONING, REACTOR DISMANTLING
BUILDINGS, DECOMMISSIONING, DEMOLITION, ENGINEERING, ENRICHED URANIUM REACTORS, ENVIRONMENTAL TRANSPORT, MASS TRANSFER, NUCLEAR FACILITIES, POPULATIONS, POWER PLANTS, POWER REACTORS, REACTORS, REGULATIONS, SAFETY STANDARDS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lewis, L; Moodenbaugh, A; Welch, D; Panchanathan, V
Brookhaven National Lab., Upton, NY (United States); National Synchrotron Light Source (United States). Funding organisation: USDOE Office of Energy Research (ER) (United States)2001
Brookhaven National Lab., Upton, NY (United States); National Synchrotron Light Source (United States). Funding organisation: USDOE Office of Energy Research (ER) (United States)2001
AbstractAbstract
No abstract available
Source
AC02-98CH10886
Record Type
Journal Article
Journal
Journal of Physics. D, Applied Physics; ISSN 0022-3727; ; v. 34(5); [10 p.]
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The history and development of the health physics and as-low-as-reasonably-achievable (ALARA) program at Duke Power Company's Oconee Nuclear Station is described as are the fundamental elements of the program and how the program works. The benefits of this health physics/ALARA program have been determined to be (a) improved quality of manpower planning and scheduling, (b) increased efficiency of shutdown activities, (c) reduced cost of shutdown, (d) immediate awareness of adverse job exposure trends, (e) better management information on exposure-related problems, (f) improved accuracy of personnel and job dose records, and (g) in general, improved outage performance and subsequent plant operation. Experience with the health physics/ALARA program is discussed in terms of (a) savings of critical path time, (b) maintaining ALARA personnel doses, and (c) record capacity factors
Primary Subject
Record Type
Journal Article
Journal
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |