Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project

Research output: Contribution to journalArticleScientificpeer-review

1 Citation (Scopus)

Abstract

The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.

Original languageEnglish
Pages (from-to)205-220
Number of pages16
JournalNuclear Technology
Volume203
Issue number2
DOIs
Publication statusPublished - 3 Aug 2018
MoE publication typeA1 Journal article-refereed

Fingerprint

Decommissioning (nuclear reactors)
decommissioning
Research reactors
reactors
Graphite
graphite
Finland
personnel
classifying
Shielding
Mass spectrometry
shielding
planning
depletion
Lithium
mass spectroscopy
lithium
sampling
histories
Irradiation

Keywords

  • activity inventory, characterization
  • Decommissioning
  • TRIGA research reactor

Cite this

@article{ce3d384d3a2242bca5564a5414ffdd93,
title = "Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project",
abstract = "The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.",
keywords = "activity inventory, characterization, Decommissioning, TRIGA research reactor",
author = "Antti R{\"a}ty and Tommi Kekki and Merja Tanhua-Tyrkk{\"o} and Tiina Lavonen and Emmi Myllykyl{\"a}",
year = "2018",
month = "8",
day = "3",
doi = "10.1080/00295450.2018.1445402",
language = "English",
volume = "203",
pages = "205--220",
journal = "Nuclear Technology",
issn = "0029-5450",
publisher = "American Nuclear Society ANS",
number = "2",

}

TY - JOUR

T1 - Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project

AU - Räty, Antti

AU - Kekki, Tommi

AU - Tanhua-Tyrkkö, Merja

AU - Lavonen, Tiina

AU - Myllykylä, Emmi

PY - 2018/8/3

Y1 - 2018/8/3

N2 - The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.

AB - The objective of the study has been to verify the calculated residual activity in the decommissioning waste of the TRIGA Mark II–type research reactor FiR 1 in Finland. Knowledge of the radioactive inventory of irradiated materials is important in the planning of decommissioning activities and is essential for predicting the radiological impact to personnel and the environment. Measurements are performed for low active material samples from outer parts of the reactor. Methods include gamma spectrometric measurements, composition measurements with mass spectrometry, oxidation measurements of especially 14C in graphite, and full combustion measurements of lithium-enriched shielding materials. Results are compared to estimates calculated with a combined Monte Carlo model of the reactor and a point-depletion code modeling the irradiation history. Decommissioning waste consists mainly of ordinary concrete, aluminum, steel, and graphite parts. Only preliminary measurements of low active samples are reported so far, but the same methods will be used later for characterizing and classifying dismantling waste. Some discussion of characterization requirements and future sampling is also included.

KW - activity inventory, characterization

KW - Decommissioning

KW - TRIGA research reactor

UR - http://www.scopus.com/inward/record.url?scp=85048131548&partnerID=8YFLogxK

U2 - 10.1080/00295450.2018.1445402

DO - 10.1080/00295450.2018.1445402

M3 - Article

AN - SCOPUS:85048131548

VL - 203

SP - 205

EP - 220

JO - Nuclear Technology

JF - Nuclear Technology

SN - 0029-5450

IS - 2

ER -