Published 1998
by Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Commission of the European Communities, Supt. of Docs., U.S. G.P.O. [distributor] in Washington, DC, Brussels, Belgium .
Written in English
Edition Notes
| Other titles | Uncertainty assessment for internal dosimetry. |
| Statement | prepared by L.H.J. Goossens ... [et al.]. |
| Series | EUR -- 16773., EUR (Series) -- 16773. |
| Contributions | Goossens, L. H. J., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology., Sandia National Laboratories. |
| The Physical Object | |
|---|---|
| Format | Microform |
| Pagination | 2 v. |
| ID Numbers | |
| Open Library | OL17702007M |
Get this from a library! Probabilistic accident consequence uncertainty analysis: uncertainty assessment for internal dosimetry. [L H J Goossens; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology.; Sandia National Laboratories.;]. We use cookies to make interactions with our website easy and meaningful, to better understand the use of our services, and to tailor advertising. Get this from a library! Probabilistic accident consequence uncertainty analysis: dispersion and deposition uncertainty assessment. [U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology.; Commission . Probabilistic Accident Consequence Uncertainty Analysis Dispersion and Deposition Uncertainty Assessment Main Report Manuscript Completed: November Date Published: January Prepared by F. T. Harper Sandia National Laboratories, USA S. C. Hora University of Hawau at Hilo, USA M. L. Young Sandia National Laboratories, USA.
Probabilistic accident consequence uncertainty analysis: Dispersion and deposition uncertainty asses. COSYMA is a system of programs and data bases, rather than a single program. The mainframe version contains three main accident consequence assessment programs together with a number of preprocessing and evaluation programs. The three main sub-systems of COSYMA are known as the NE, NL, and FL sub-systems (Figure A-4). probabilistic accident consequence codes: MACCS(1) in the United States and COSYMA(2) in Europe. Uncertainty analyses have been performed with predecessors of both codes, whereby the probability distributions utilised were assigned primarily by the consequence . Aug 01, · The development of two probabilistic accident consequence codes sponsored by the European Commission and the United States Nuclear Regulatory Commiss We use cookies to enhance your experience on our grupo-operativo-gei-porcino.com continuing to Cited by:
Jow H-N, Sprung J L, Chanin D I, Helton J C and Rollstin J A Reactor Accident Consequence Analysis Code (MACCS) SANDC (Albuquerque, NM: Sandia National Laboratories) Little M P, Muirhead C R, Goossens L H J, Kraan B C P, Cooke R M, Harper F T and Hora S C Probabilistic Accident Consequence Uncertainty Analysis. Late Health Author: M P Little. probabilistic accident consequence assessment system COSYMA 3 to provide an input to identifying future R&D priorities. This report describes the analysis of the uncertainty in the model predictions resulting from uncertainty in the values to be assigned to the input parameters describing internal and external dosimetry and consumption rates. Aug 01, · Uncertainty analysis of the dose calculation module of the COSYMA accident consequence assessment code has been undertaken, involving the following s We use cookies to enhance your experience on our grupo-operativo-gei-porcino.com continuing to Author: J.D. Harrison, J. Boardman, J.A. Jones, A. Khursheed, B.C.P. Kraan, A.W. Phipps (Invited). Aug 01, · A set of model parameters was identified which contribute most to the uncertainties of endpoints. Probabilistic accident consequence assessments with weather sequences were performed for each of sample sets derived from the uncertainty distributions of these parameters by Latin hypercube grupo-operativo-gei-porcino.com by: 3.
