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Title: RADTRAD: A simplified model for RADionuclide Transport and Removal And Dose estimation

Abstract

This report documents the RADTRAD computer code developed for the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Reactor Regulation (NRR) to estimate transport and removal of radionuclides and dose at selected receptors. The document includes a users` guide to the code, a description of the technical basis for the code, the quality assurance and code acceptance testing documentation, and a programmers` guide. The RADTRAD code can be used to estimate the containment release using either the NRC TID-14844 or NUREG-1465 source terms and assumptions, or a user-specified table. In addition, the code can account for a reduction in the quantity of radioactive material due to containment sprays, natural deposition, filters, and other natural and engineered safety features. The RADTRAD code uses a combination of tables and/or numerical models of source term reduction phenomena to determine the time-dependent dose at user-specified locations for a given accident scenario. The code system also provides the inventory, decay chain, and dose conversion factor tables needed for the dose calculation. The RADTRAD code can be used to assess occupational radiation exposures, typically in the control room; to estimate site boundary doses; and to estimate dose attenuation due to modification of a facility or accidentmore » sequence.« less

Authors:
; ;  [1];  [2]
  1. Sandia National Labs., Albuquerque, NM (United States)
  2. ITSC, Albuquerque, NM (United States)
Publication Date:
Research Org.:
ITSC, Albuqerque, NM (United States); Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Reactor Regulation; Sandia National Labs., Albuquerque, NM (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI Identifier:
604405
Report Number(s):
NUREG/CR-6604; SAND-98-0272
ON: TI98005195; TRN: 98:005519
DOE Contract Number:  
AC04-94AL85000
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Apr 1998
Country of Publication:
United States
Language:
English
Subject:
56 BIOLOGY AND MEDICINE, APPLIED STUDIES; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; 22 NUCLEAR REACTOR TECHNOLOGY; CONTAINMENT; DECAY; FILTERS; QUALITY ASSURANCE; SOURCE TERMS; SPRAYS; TRANSPORT; RADIATION DOSES; R CODES; REACTOR ACCIDENTS; OCCUPATIONAL EXPOSURE; RADIONUCLIDE MIGRATION; TIME DEPENDENCE

Citation Formats

Humphreys, S.L., Miller, L.A., Monroe, D.K., and Heames, T.J.. RADTRAD: A simplified model for RADionuclide Transport and Removal And Dose estimation. United States: N. p., 1998. Web. doi:10.2172/604405.
Humphreys, S.L., Miller, L.A., Monroe, D.K., & Heames, T.J.. RADTRAD: A simplified model for RADionuclide Transport and Removal And Dose estimation. United States. doi:10.2172/604405.
Humphreys, S.L., Miller, L.A., Monroe, D.K., and Heames, T.J.. Wed . "RADTRAD: A simplified model for RADionuclide Transport and Removal And Dose estimation". United States. doi:10.2172/604405. https://www.osti.gov/servlets/purl/604405.
@article{osti_604405,
title = {RADTRAD: A simplified model for RADionuclide Transport and Removal And Dose estimation},
author = {Humphreys, S.L. and Miller, L.A. and Monroe, D.K. and Heames, T.J.},
abstractNote = {This report documents the RADTRAD computer code developed for the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Reactor Regulation (NRR) to estimate transport and removal of radionuclides and dose at selected receptors. The document includes a users` guide to the code, a description of the technical basis for the code, the quality assurance and code acceptance testing documentation, and a programmers` guide. The RADTRAD code can be used to estimate the containment release using either the NRC TID-14844 or NUREG-1465 source terms and assumptions, or a user-specified table. In addition, the code can account for a reduction in the quantity of radioactive material due to containment sprays, natural deposition, filters, and other natural and engineered safety features. The RADTRAD code uses a combination of tables and/or numerical models of source term reduction phenomena to determine the time-dependent dose at user-specified locations for a given accident scenario. The code system also provides the inventory, decay chain, and dose conversion factor tables needed for the dose calculation. The RADTRAD code can be used to assess occupational radiation exposures, typically in the control room; to estimate site boundary doses; and to estimate dose attenuation due to modification of a facility or accident sequence.},
doi = {10.2172/604405},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Apr 01 00:00:00 EST 1998},
month = {Wed Apr 01 00:00:00 EST 1998}
}

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