Assessment of uncertainties in early off-site consequences from nuclear reactor accidents

Journal Article · Sun Apr 01 04:00:00 EDT 1990 · Nuclear Technology; (USA)

OSTI ID:6499082

Madni, I K; Cazzoli, E G ^[1]; Khatib-Rahbar, M ^[2]

---

1. Brookhaven National Lab., Dept. of Nuclear Energy, Upton, NY (US)
2. Energy Research, Inc., Rockville, MD (US)

A simplified approach has been developed to calculate uncertainties in early off-site consequences from nuclear reactor accidents. The consequence model (SMART) is based on a solution procedure that uses simplified meteorology and involves direct analytic integration of air concentration equations over time and position. This is different from the discretization approach currently used in the CRAC2 and MACCS codes. The SMART code is fast running, thereby providing a valuable tool for sensitivity and uncertainty studies. The code was benchmarked against both MACCS version 1.4 and CRAC2. Results of benchmarketing and detailed sensitivity and uncertainty analyses using SMART are presented.

• OSTI ID: 6499082
• Journal Information: Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 90:1; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220900* -- Nuclear Reactor Technology-- Reactor Safety
54 ENVIRONMENTAL SCIENCES
540130 -- Environment
Atmospheric-- Radioactive Materials Monitoring & Transport-- (1990-)
ACCIDENTS
C CODES
CALCULATION METHODS
COMPUTER CODES
ENVIRONMENTAL TRANSPORT
M CODES
MASS TRANSFER
RADIONUCLIDE MIGRATION
REACTOR ACCIDENTS
RISK ASSESSMENT
S CODES