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Decomissioning of nuclear reactors - methods for calculation of radionuclide inventories in contaminated BWR systems

Abstract

The purpose of the study has been to develop and demonstrate calculation models for the prediction of radionuclide inventories in contaminated systems in the Nordic BWRs at the time of decommissioning. Oskarshamn 2 was selected as reference reactor for the study. The study is divided in radionuclide inventories of activated corrosion products, and inventories of fission products and actinides from leaking fuel. The study is restricted to contamination outside the reactor pressure vessel. Inventories of activated corrosion products on primary system surfaces were predicted with the ABB Atom computer code BKM-CRUD. The calculations were performed for an extended operation time up to year 2010 for the nuclides Co60, Co58, Zn65 and Mn54. A special set of calculations were also made covering the non-standard nuclides Fe55, Ni59, No63 and Mo93. ABB Atom has carried out a comprehensive program on shutdown dose rates and activity measurements in delivered BWRs. The resulting data base have been used in the study to derive conversion factors for evaluation of contamination levels in secondary systems from the BKM-CRUD results for primary systems. Fission products and actinides were treated by defining two different fuel leakage scenarios. The first one corresponds to a rather stable situation, with an  More>>
Authors:
Publication Date:
Apr 26, 1991
Product Type:
Technical Report
Report Number:
ABB-ATOM-RM-91-59
Reference Number:
SCA: 210100; PA: AIX-23:031855; SN: 92000710133
Resource Relation:
Other Information: PBD: 26 Apr 1991
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; REACTOR COOLING SYSTEMS; SURFACE CONTAMINATION; B CODES; BWR TYPE REACTORS; COMPUTER CALCULATIONS; CORROSION PRODUCTS; DEPOSITS; EXPERIMENTAL DATA; FISSION PRODUCTS; RADIOACTIVITY; REACTOR DECOMMISSIONING; REACTOR DISMANTLING; 210100; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED
OSTI ID:
10135845
Research Organizations:
ABB Atom AB, Vaesteraas (Sweden)
Country of Origin:
Sweden
Language:
English
Other Identifying Numbers:
Other: ON: DE92624240; CNN: Project SSI-P--589-90; TRN: SE9200030031855
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
SWDN
Size:
60 p.
Announcement Date:
Jul 05, 2005

Citation Formats

Lundgren, K. Decomissioning of nuclear reactors - methods for calculation of radionuclide inventories in contaminated BWR systems. Sweden: N. p., 1991. Web.
Lundgren, K. Decomissioning of nuclear reactors - methods for calculation of radionuclide inventories in contaminated BWR systems. Sweden.
Lundgren, K. 1991. "Decomissioning of nuclear reactors - methods for calculation of radionuclide inventories in contaminated BWR systems." Sweden.
@misc{etde_10135845,
title = {Decomissioning of nuclear reactors - methods for calculation of radionuclide inventories in contaminated BWR systems}
author = {Lundgren, K}
abstractNote = {The purpose of the study has been to develop and demonstrate calculation models for the prediction of radionuclide inventories in contaminated systems in the Nordic BWRs at the time of decommissioning. Oskarshamn 2 was selected as reference reactor for the study. The study is divided in radionuclide inventories of activated corrosion products, and inventories of fission products and actinides from leaking fuel. The study is restricted to contamination outside the reactor pressure vessel. Inventories of activated corrosion products on primary system surfaces were predicted with the ABB Atom computer code BKM-CRUD. The calculations were performed for an extended operation time up to year 2010 for the nuclides Co60, Co58, Zn65 and Mn54. A special set of calculations were also made covering the non-standard nuclides Fe55, Ni59, No63 and Mo93. ABB Atom has carried out a comprehensive program on shutdown dose rates and activity measurements in delivered BWRs. The resulting data base have been used in the study to derive conversion factors for evaluation of contamination levels in secondary systems from the BKM-CRUD results for primary systems. Fission products and actinides were treated by defining two different fuel leakage scenarios. The first one corresponds to a rather stable situation, with an average leakage rate of 1 `standard pin hole` (i.e. 2 MBq/s Xe133). The second scenario means more severe fuel leakage every 10 years (200 MBq/s Xe133). The radioactive inventories in different part of the plant were calculated by combining the surface areas with the calculated contamination levels in the different systems. The uncertainty in total activity inventory has been estimated to not exceed a factor of 2. The uncertainty in total activity inventory has been to not exceed a factor of 2. The estimated inventories in this study has been compared to the results from other studies, and a reasonable agreement was achieved.}
place = {Sweden}
year = {1991}
month = {Apr}
}