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Safety in the final disposal of radioactive waste. Final report

Abstract

During 1994-1997 a project on the disposal of radioactive waste was carried out as part of the NKS program. The objective of the project was to give authorities and waste producers in the Nordic countries background material for determinations about the management and disposal of radioactive waste. The project NKS/AFA-1 was divided into three sub-projects: AFA-1.1, AFA-1.2 and AFA-1.3. AFA-1.1 dealt with waste characterisation, AFA-1.2 dealt with performance assessment for repositories and AFA-1.3 dealt with Environmental Impact Assessment (EIA). The studies mainly focused on the management of long-lived low- and intermediate-level radioactive waste from research, hospitals and industry. The AFA-1.1 study included an overview on waste categories in the Nordic countries and methods to determine or estimate the waste content. The results from the AFA-1.2 study include a short overview of different waste management systems existing and planned in the Nordic countries. However, the main emphasis of the study was a general discussion of methodologies developed and employed for performance assessments of waste repositories. Some of the phenomena and interactions relevant for generic types of repository were discussed as well. Among the different approaches for the development of scenarios for safety and performance assessments one particular method, the Rock Engineering  More>>
Authors:
Broden, K; Carugati, S; Brodersen, K [1] 
  1. and others
Publication Date:
Dec 01, 1997
Product Type:
Technical Report
Report Number:
NKS-FR-3(97)
Reference Number:
SCA: 052000; 056000; PA: AIX-30:013854; EDB-99:077842; SN: 99002073397
Resource Relation:
Other Information: DN: 33 refs.; PBD: Dec 1997
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CONTAINERS; COORDINATED RESEARCH PROGRAMS; DENMARK; FINLAND; ICELAND; INTERMEDIATE-LEVEL RADIOACTIVE WASTES; LOW-LEVEL RADIOACTIVE WASTES; NORWAY; RADIOACTIVE WASTE MANAGEMENT; RECOMMENDATIONS; SAFETY; SWEDEN; WASTE FORMS; 052000; 056000; WASTE MANAGEMENT; LEGISLATION AND REGULATIONS
OSTI ID:
10147512
Research Organizations:
Nordisk Kernesikkerhedsforskning, Roskilde (Denmark)
Country of Origin:
Denmark
Language:
English
Other Identifying Numbers:
Other: ON: DE99618043; CNN: Contract NKS/AFA-1; ISBN 87-7893-023-5; TRN: DK9900029013854
Availability:
OSTI; NTIS; INIS
Submitting Site:
DKN
Size:
[85] p.
Announcement Date:
Sep 09, 1999

Citation Formats

Broden, K, Carugati, S, and Brodersen, K. Safety in the final disposal of radioactive waste. Final report. Denmark: N. p., 1997. Web.
Broden, K, Carugati, S, & Brodersen, K. Safety in the final disposal of radioactive waste. Final report. Denmark.
Broden, K, Carugati, S, and Brodersen, K. 1997. "Safety in the final disposal of radioactive waste. Final report." Denmark.
@misc{etde_10147512,
title = {Safety in the final disposal of radioactive waste. Final report}
author = {Broden, K, Carugati, S, and Brodersen, K}
abstractNote = {During 1994-1997 a project on the disposal of radioactive waste was carried out as part of the NKS program. The objective of the project was to give authorities and waste producers in the Nordic countries background material for determinations about the management and disposal of radioactive waste. The project NKS/AFA-1 was divided into three sub-projects: AFA-1.1, AFA-1.2 and AFA-1.3. AFA-1.1 dealt with waste characterisation, AFA-1.2 dealt with performance assessment for repositories and AFA-1.3 dealt with Environmental Impact Assessment (EIA). The studies mainly focused on the management of long-lived low- and intermediate-level radioactive waste from research, hospitals and industry. The AFA-1.1 study included an overview on waste categories in the Nordic countries and methods to determine or estimate the waste content. The results from the AFA-1.2 study include a short overview of different waste management systems existing and planned in the Nordic countries. However, the main emphasis of the study was a general discussion of methodologies developed and employed for performance assessments of waste repositories. Some of the phenomena and interactions relevant for generic types of repository were discussed as well. Among the different approaches for the development of scenarios for safety and performance assessments one particular method, the Rock Engineering System (RES), was chosen to be tested by demonstration. The possible interactions and their safety significance were discussed, employing a simplified and generic Nordic repository system as the reference system. New regulations for the inventory of a repository may demand new assessments of old radioactive waste packages. The existing documentation of a waste package is then the primary information source although additional measurements may be necessary. (EG) 33 refs.}
place = {Denmark}
year = {1997}
month = {Dec}
}