Published 2003 | Version v1
Miscellaneous

Uncertainty analysis of the calculated radioactivity in liquid effluent released as batch mode from a nuclear power plant

  • 1. KAERI, Taejon (Korea, Republic of)

Description

A series of factors such as sampling, pretreatment, measurement, volume estimation which induces uncertainty of the calculated radioactivity in liquid effluent released from a nuclear power plant were analyzed. It is innately impossible to estimate exact error of the calculated radioactivity, since most of the input parameters are determined by a single measurement and true value of the released radioactivity cannot be known. In this paper, a systematic model to calculate uncertainty of the released liquid radioactivity was developed based upon the guidance report published by the ISO in 1993, and the model was applied to a set of hypothetical batch release conditions. As a result, the priority of each input parameter was turned out to be (1) wastewater volume, (2) sample volume, and (3) measured radioactivity of the sample. In addition, probability distribution of the released radioactivity was simulated by Monte Carlo method combining the probability distribution of each input parameter. It was shown that the radioactivity released to the environment, which has been reported as a single value, has a certain form of probability distribution

Part of:
Proceedings of the Korean Radioactive Waste Society Fall, 2003

Additional details

Publishing Information

Publisher
KRWS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Radioactive Waste Society Fall, 2003
Imprint Pagination
724 p.
Journal Page Range
p. 562-571

Conference

Title
2003 Fall Meeting of the Korean Radioactive Waste Society
Dates
27-29 Nov 2003
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36017126
Subject category
S54: ENVIRONMENTAL SCIENCES;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; LIQUID WASTES; MONTE CARLO METHOD; NUCLEAR POWER PLANTS; PROBABILITY
Descriptors DEC
CALCULATION METHODS; NUCLEAR FACILITIES; POWER PLANTS; SIMULATION; THERMAL POWER PLANTS; WASTES

Optional Information

Notes
17 refs, 1 fig, 1 tab