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InterRAS


ANSI79 American National Standard for Decay Heat Power in Light Water
Reactors, ANSI/ANS-5.1, American Nuclear Society, La Grange Park, IL, December 1979.
ANSI84 American National Standard Radioactive Source Term for Normal
Operation of Light-Water Reactors, ANSI/ANS 18 .1, American Nuclear Society, La Grange Park, IL, December 1984.
ASME93 ASME 1993 C. A Meyer, R. B. McClintock, G. J. Silvestri, and R. C.
Spencer, Jr., ASME Steam Tables: Thermodynamic and Transport Properties of Steam, 6th Ed., American Society of Mechanical Engineers Press, New York, 1993.
DOE84 U.S. Department of Energy - Atmospheric Science and Power Production,
DOE, DOE/TIC-27601, 1984.
DOE95 FRMAC Assessment Manual, vol. 1, Methods, and vol. 2, Tables, Charts,
Worksheets, Glossary, Reference, Index, interim version, U.S. Department of Energy, Washington, D C., July 1995.
EGG75 Structures Shielding from Cloud and Fallout Gamma-Ray Sources for
Assessing the Consequence of Reactor Accidents, Burson E.G., EGG- 1183-1670, 1975.
EPA70 Turner, Workbook of Atmospheric Dispersion Estimates, EPA, January
1970.
EPA88 Keith F. Eckerman, Anthony B. Wolbarst, and Allan . B. Richardson,
Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, EPA-520/1- 88-020, Federal Guidance Report No. 11, Environmental Protection Agency, Washington, D.C., September 1988.
EPA92 Manual of Protective Action Guides and Protective Actions for Nuclear
Incidents, U.S. EPA, EPA 400-R-92-001, May 1992.
EPA93 External Exposure to Radionuclides in Air, Water, and Soil, Federal
Guidance Report No. 12, U.S. EPA, EPA-402-R-93-081, September 1993.
EPA94 U.S. EPA, PAG Subcommittee Report on Implementation of EPA's Dose
Limits for Emergency Workers, July 12, 1994.
FEMA87 Guidance on Offsite Emergency Radiation Measurement Systems Phase 2 -
The Milk Pathway, FEMA, FEMA REP-12, September 1987.
IAEA74 International Atomic Energy Agency, Evaluation of Radiation Emergencies
and Accidents: Selected Criteria and Data, Technical Reports Series No. 152, IAEA, Vienna (1974).
IAEA86 Derived Intervention Levels for Application in Controlling Radiation Doses
to the Public in the event of a Nuclear Accident or Radiological Emergency, Safety Series No. 81, IAEA, Vienna, (1986).
IAEA94 International Atomic Energy Agency, Intervention Criteria in a Nuclear or
Radiation Emergency, Safety Series No. 109, IAEA, Vienna (1994).
IAEA94a International Atomic Energy Agency, Guidelines for Agricultural
Countermeasures Following an Accidental Release of Radionuclides, Technical Report Series No. 363, IAEA, Vienna, (1994).
IAEA96 International Atomic Energy Agency, International Basic Safety Standards
for Protection against Ionizing Radiation and for the Safety of Radiation Sources, Safety Series 115, IAEA, Vienna, (1996).
IAEA97 International Atomic Energy Agency, Method for the Development of
Emergency Response Preparedness for Nuclear or Radiological Accidents, IAEA-TECDOC-953, IAEA, Vienna (1997).
ICRP75 Report of the Task Group on Reference Man, ICRP-23, International
Commission on Radiological Protection, October 1975.
ICRU92 Measurement of Dose Equivalents form External Photon and Electron
Radiations, ICRU Report 47, April 1992, International Commission on Radiation Units and Measurements, Bethesda Maryland
NRC75 WASH-1400 Reactor Safety Study: An Assessment of Accident Risks in
U S. Commercial Nuclear Power Plants, App. VI, Calculation of Reactor Accident Consequences, WASH-1400 (NUREG 75/014), U.S. Nuclear Regulatory Commission, Washington, D.C., October 1975.
NRC77 U.S. NRC, Regulatory Guide 1.109, Calculation of Annual Doses to Man
from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, October 1977.
NRC79a NUREG-600 Investigation Into the March 28, 1979, Three Mile Island
Accident by the Office of Inspection and Enforcement, U. S. Nuclear Regulatory Commission, Washington, D.C., August 1979.
NRC79b Allan S. Benjamin, David J. McCloskey, Dana A. Powers, and Stephen A.
Dupree, Spent Fuel Heatup Following Loss of Water During Storage, NUREG/CR-0649 (SAND77-1371, R-3), Sandia Laboratories, Albuquerque, NM, March 1979.
NRC80 Criteria for Preparation and Evaluation of Radiological Emergency
Response Plans and Preparedness in Support of Nuclear Power Plants, NUREG-0654 (FEMA-REP-1), Rev. 1, U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency, Washington, D.C., November 1980.
NRC83 John E. Till and H. Robert Meyer - Radiological Assessment: A Textbook
on Environmental Dose Analysis, NRC, NUREG/CR-3332, September 1983.
NRC83a A. L. Camp, et al., Light Water Reactor Hydrogen Manual, NUREG/CR-
2726 (SAND82-1137, R3), U.S. Nuclear Regulatory Commission, Washington, D.C., June 1983.

NRC83b

J. T. Larkins and M. A. Cunningham, Nuclear-Power-Plant-Severe- Accident Research Plan, U. S. Nuclear Regulatory Commission, Washington, D.C., January 1983.

NRC88

T. J. McKenna and J. G. Glitter, Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents, NUREG-1228, U. S. Nuclear Regulatory Commission, Washington, D.C., October 1988.

NRC90

Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants, NUREG-1150, vol. 1, U.S. Nuclear Regulatory Commission, Washington, D.C., December 1990.

NRC91

S. A. McGuire, Chemical Toxicity of Uranium Hexafluoride Compared to Acute Effects of Radiation, NUREG-1391, Nuclear Regulatory Commission, Washington, D.C., January 1991.

NRC92

L. Soffer, Accident Source Terms for Light Water Nuclear Power Plants, U.S. NRC, NUREG-1465, Draft for Comment, June 1992.

NRC93

Response Technical Manual, RTM93, U.S. NRC, NUREG/BR-0150, Volume 1, November 1993.

NRC94

RASCAL Version 2.1, Users Guide, U.S. NRC, NUREG/CR-5247, Vol. 1, Rev. 2, 1994.

NRC96

J. Trefethen, Response Technical Manual, RTM 96, U.S. NRC, NUREG/BR-0150, Volume 1, March 1996.

NUMARC92

Methodology for Development of Emergency Action Levels, NuclearManagement Council Inc., January 1992, Washington D.C. USA



 
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