RASCAL 4.l: evaluation system for the analysis of the radiological consequences
Creators
Description
Recently the Spanish Nuclear Safety Council (CSN) has promoted the replacement of the code used in the Spanish Nuclear Power Plants to estimate potential and actual doses due to atmospheric releases. IRDAM Code (interactive Rapid Dose Assessment Model, 1983) by RASCAL Code version 4.1 (Radiological Assessment System for consequence Analysis). This code was developed by the NRC (Nuclear Regulatory Commission) to evaluate releases from nuclear power plants, spent fuel storage pools and casks, fuel cycle facilities and radioactive material handling facilities. RASCAL was officially requested to the Spanish nuclear power plants in February 1st, 2012, and it can be used for external dose assessment and to evaluate the recommended protective action for the public in a specific situation (sheltering, prophylaxis, evacuation, etc.). (Author)
Additional details
Additional titles
- Original title (Spanish)
- RASCAL 4.1: Sistema de evaluacion para el analisis de las consecuencias radiologicas
Publishing Information
- Journal Title
- Nuclear Espana (1996)
- Journal Volume
- 327
- Journal Page Range
- p. 49-51
- ISSN
- 1137-2885
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- Spain
- INIS RN
- 43066878
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- FUEL CYCLE; NUCLEAR ENERGY; NUCLEAR FACILITIES; NUCLEAR FUELS; NUCLEAR POWER PLANTS; POWER REACTORS; RISK ASSESSMENT; SPENT FUEL STORAGE
- Descriptors DEC
- ENERGY; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR MATERIALS; REACTORS; STORAGE; THERMAL POWER PLANTS