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Safety and sensitivity analyses of a generic geologic disposal system for high-level radioactive waste

Technical Report:

Abstract

This report describes safety and sensitivity analyses of a generic geologic disposal system for HLW, using a GSRW code and an automated sensitivity analysis methodology based on the Differential Algebra. An exposure scenario considered here is based on a normal evolution scenario which excludes events attributable to probabilistic alterations in the environment. The results of sensitivity analyses indicate that parameters related to a homogeneous rock surrounding a disposal facility have higher sensitivities to the output analyzed here than those of a fractured zone and engineered barriers. The sensitivity analysis methodology provides technical information which might be bases for the optimization of design of the disposal facility. Safety analyses were performed on the reference disposal system which involve HLW in amounts corresponding to 16,000 MTU of spent fuels. The individual dose equivalent due to the exposure pathway ingesting drinking water was calculated using both the conservative and realistic values of geochemical parameters. In both cases, the committed dose equivalent evaluated here is the order of 10{sup -7}Sv, and thus geologic disposal of HLW may be feasible if the disposal conditions assumed here remain unchanged throughout the periods assessed here. (author).
Authors:
Kimura, Hideo; Takahashi, Tomoyuki; Shima, Shigeki; Matsuzuru, Hideo [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Nov 01, 1994
Product Type:
Technical Report
Report Number:
JAERI-Research-94-028
Reference Number:
SCA: 052002; PA: JPN-94:012181; EDB-95:019961; SN: 95001319989
Resource Relation:
Other Information: PBD: Nov 1994
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; HIGH-LEVEL RADIOACTIVE WASTES; UNDERGROUND DISPOSAL; SAFETY; SENSITIVITY ANALYSIS; SOURCE TERMS; GEOLOGIC MODELS; RADIONUCLIDE MIGRATION; SOLUBILITY; GROUND WATER; GEOCHEMISTRY; COMPUTERIZED SIMULATION; G CODES; 052002; WASTE DISPOSAL AND STORAGE
OSTI ID:
10109327
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE95737273; TRN: JP9412181
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
58 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kimura, Hideo, Takahashi, Tomoyuki, Shima, Shigeki, and Matsuzuru, Hideo. Safety and sensitivity analyses of a generic geologic disposal system for high-level radioactive waste. Japan: N. p., 1994. Web.
Kimura, Hideo, Takahashi, Tomoyuki, Shima, Shigeki, & Matsuzuru, Hideo. Safety and sensitivity analyses of a generic geologic disposal system for high-level radioactive waste. Japan.
Kimura, Hideo, Takahashi, Tomoyuki, Shima, Shigeki, and Matsuzuru, Hideo. 1994. "Safety and sensitivity analyses of a generic geologic disposal system for high-level radioactive waste." Japan.
@misc{etde_10109327,
title = {Safety and sensitivity analyses of a generic geologic disposal system for high-level radioactive waste}
author = {Kimura, Hideo, Takahashi, Tomoyuki, Shima, Shigeki, and Matsuzuru, Hideo}
abstractNote = {This report describes safety and sensitivity analyses of a generic geologic disposal system for HLW, using a GSRW code and an automated sensitivity analysis methodology based on the Differential Algebra. An exposure scenario considered here is based on a normal evolution scenario which excludes events attributable to probabilistic alterations in the environment. The results of sensitivity analyses indicate that parameters related to a homogeneous rock surrounding a disposal facility have higher sensitivities to the output analyzed here than those of a fractured zone and engineered barriers. The sensitivity analysis methodology provides technical information which might be bases for the optimization of design of the disposal facility. Safety analyses were performed on the reference disposal system which involve HLW in amounts corresponding to 16,000 MTU of spent fuels. The individual dose equivalent due to the exposure pathway ingesting drinking water was calculated using both the conservative and realistic values of geochemical parameters. In both cases, the committed dose equivalent evaluated here is the order of 10{sup -7}Sv, and thus geologic disposal of HLW may be feasible if the disposal conditions assumed here remain unchanged throughout the periods assessed here. (author).}
place = {Japan}
year = {1994}
month = {Nov}
}