RASCAL2. 0

Miscellaneous · Fri Sep 01 00:00:00 EDT 1989

OSTI ID:6272501

Sjoreen, A L ^[1]; Athey, G F ^[2]; Ramsdell, J V ^[3]; McKeena, T J ^[4]

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1. Oak Ridge National Lab., TN (United States)
2. Phoenix Associates Inc., Bethesda, MD (United States)
3. Pacific Northwest Lab., Richland, WA (United States)
4. Nuclear Regulatory Commission, Washington, DC (United States)

RASCAL2.0 (Radiologic Assessment System for Consequence Analysis) has been developed for use during response to radiological emergencies. The model is designed to provide a rough comparison to EPA Protective Action Guidance and thresholds for acute health effects. RASCAL will be used by the NRC personnel who report to the site of a nuclear accident to conduct an independent evaluation of dose and consequence projections. The model was developed to allow consideration of the dominant aspects of source term, transport, dose, and consequences. Graphics were designed for use on the COMPAQ Portable III microcomputer used by the NRC response personnel. The model can be run on any DOS system, and the results can be displayed as text or maps. Substantial revisions to RASCAL 1.3 have required the release of this new version of the system. Two new models have been added to RASCAL 2.0. The first, FM-DOSE, computes doses from environmental concentrations. The second DECAY, computes radiologic decay and ingrowth over a selected time period. The model that was previously the whole of RASCAL has been renamed ST-DOSE. Source term, transport, and dose calculations in ST-DOSE all have been modified, and the input and output screens have been revised based on user comments and suggestions. RASCAL is reviewed on an ongoing basis and will be further revised to reflect advances in our understanding of reactor accidents.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: NRC/AEOD; Nuclear Regulatory Commission, Washington, DC (United States). Office for Analysis and Evaluation of Operational Data
• OSTI ID: 6272501
• Report Number(s): ESTSC/NRC-000004IBMPC01
• Resource Relation: Other Information: Compiling the C source requires two different versions of Vermont Creative Software's Vermont Views libraries, used only for data input. These proprietary libraries are not included
• Country of Publication: United States
• Language: English

Related Subjects

99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
22 GENERAL STUDIES OF NUCLEAR REACTORS
R CODES
REACTOR ACCIDENTS
COMPUTER PROGRAM DOCUMENTATION
DIFFUSION
EARTH ATMOSPHERE
FISSION PRODUCT RELEASE
I CODES
M CODES
MANUALS
MICROCOMPUTERS
ACCIDENTS
COMPUTER CODES
COMPUTERS
DIGITAL COMPUTERS
DOCUMENT TYPES
990200* - Mathematics & Computers
220900 - Nuclear Reactor Technology- Reactor Safety
220500 - Nuclear Reactor Technology- Environmental Aspects