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The solubility of U, Np, Pu, Th and Tc in a geological disposal vault for used nuclear fuel

Abstract

This document describes the solubility model used to calculate the concentrations of uranium, thorium, technetium, neptunium and plutonium in a geological disposal vault for used nuclear fuel. This model is incorporated in the vault model of SYVAC3-CC3 - the third generation of the Systems Variability Analysis Code used to assess the long-term safety of the disposal of Canada`s nuclear fuel waste. The data for the solubility model and the sources for these data are also reported.
Publication Date:
Dec 01, 1989
Product Type:
Technical Report
Report Number:
AECL-10009
Reference Number:
SCA: 052002; 540230; 540250; PA: AIX-23:037160; SN: 92000726297
Resource Relation:
Other Information: PBD: Dec 1989
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 54 ENVIRONMENTAL SCIENCES; SPENT FUELS; SOLUBILITY; UNDERGROUND DISPOSAL; WATER INFLUX; GROUND WATER; NEPTUNIUM; PLUTONIUM; RADIOACTIVE WASTE DISPOSAL; S CODES; TECHNETIUM; THORIUM; URANIUM; 052002; 540230; 540250; WASTE DISPOSAL AND STORAGE; RADIOACTIVE MATERIALS MONITORING AND TRANSPORT; SITE RESOURCE AND USE STUDIES
OSTI ID:
10139854
Research Organizations:
Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Nuclear Research Establishment
Country of Origin:
Canada
Language:
English
Other Identifying Numbers:
Other: ON: DE92627044; TRN: CA9200259037160
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
131 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Lemire, R J, and Garisto, F. The solubility of U, Np, Pu, Th and Tc in a geological disposal vault for used nuclear fuel. Canada: N. p., 1989. Web.
Lemire, R J, & Garisto, F. The solubility of U, Np, Pu, Th and Tc in a geological disposal vault for used nuclear fuel. Canada.
Lemire, R J, and Garisto, F. 1989. "The solubility of U, Np, Pu, Th and Tc in a geological disposal vault for used nuclear fuel." Canada.
@misc{etde_10139854,
title = {The solubility of U, Np, Pu, Th and Tc in a geological disposal vault for used nuclear fuel}
author = {Lemire, R J, and Garisto, F}
abstractNote = {This document describes the solubility model used to calculate the concentrations of uranium, thorium, technetium, neptunium and plutonium in a geological disposal vault for used nuclear fuel. This model is incorporated in the vault model of SYVAC3-CC3 - the third generation of the Systems Variability Analysis Code used to assess the long-term safety of the disposal of Canada`s nuclear fuel waste. The data for the solubility model and the sources for these data are also reported.}
place = {Canada}
year = {1989}
month = {Dec}
}