During decommissioning of nuclear facilities, it is generally thought that the risk is relatively low after high activity inventory such as the spent fuel is removed. However, dismantlement works may be carried out with nonmultiple barriers with a nonregular process depending mainly on human activities. Moreover, fire or gas incidents caused by conventional industry methods may lead to accidents with radioactivity release. This means more attention is necessary for safer dismantlement, especially for nuclear reactors with high activity. Therefore, utilization of risk information based on risk assessment of the decommissioning was proposed. A method of risk assessment for decommissioning was developed and applied for the dismantlement of typical reactor facilities and nuclear fuel facilities (a uranium enrichment plant and a reprocessing plant). The results show that the consequences of such troubles are low but their occurrences are still not negligible. This fact is supported by past trouble cases. Taking into account the risk assessment results, a methodology to secure the safety of decommissioning was proposed. It consists of four steps, i.e., (1) risk-informed approach, (2) graded approach, (3) phased approach, and (4) layered approach and the results can be reflected to the management and regulation. The regulation means, for example, the review of decommissioning plan or the operational safety program, the periodic safety inspections and usual monitoring. The methodology can evaluate the risk level of decommissioning more objectively and enable reasonable regulation based on the risk level. This leads to the appropriate distribution of resources for safety enhancement.

1.
Central Research Institute of Electric Power Industry
, 2007,
Handbook for Radiation Dose Assessment During Nuclear Power Plant Decommissioning
, Tokyo, Japan, in Japanese.
2.
Smith
,
R. I.
,
Konzek
,
G. J.
, and
Kennedy
,
W. E.
, Jr.
, 1978, “
Technology, Safety and Cost of Decommissioning Reference Pressurized Water Reactor Power Station
,” NUREG/CR-0130, Richland, WA.
3.
Oak
,
H. D.
,
Holter
,
G. M.
,
Kennedy
,
W. E.
, Jr.
, and
Konzek
,
G. J.
, 1980, “
Technology, Safety and Cost of Decommissioning Reference Boiling Water Reactor Power Station
,” NUREG/CR-0672, Richland, WA.
4.
Iguchi
,
Y.
,
Baba
,
T.
,
Kawakami
,
H.
,
Kitahara
,
T.
,
Watanabe
,
A.
, and
Kodama
,
M.
, 2007, “
Study for Radionuclide Transfer Ratio of Aerosols Generated During Heat Cutting
,” Paper No. ICEM07-7139.
5.
Hattori
,
T.
,
Takada
,
Y.
,
Ichiji
,
T.
,
Sasaki
,
M.
, and
Matsumura
,
T.
, 2005, “
Parameter Experimental Study for Public Dose Assessment in Decommissioning
,” Paper No. ICEM05-1190.
6.
Shimada
,
T.
,
Ohsima
,
S.
,
Ishigami
,
T.
, and
Yanagihara
,
S.
, 2005, “
Development of Public Dose Assessment Code for Decommissioning of Nuclear Reactors (DECDOSE)
,” Paper No. ICEM05-1351.
7.
Iguchi
,
Y.
,
Baba
,
T.
, and
Kawakami
,
H.
, 2006, “
Study for Nuclide Transfer Ratio of Particles Generated by Thermal Cutting
,” Paper No. ICONE14-89139.
8.
Japan Power Engineering and Inspection Corporation
, 2000, “
Study of Radiation Dose Assessment for Commercial Power Reactor During Decommissioning (Oversea Research—UK)
,” Tokyo, Japan, in Japanese.
9.
International Atomic Energy Agency
, 2001, “
Generic Model for Use in Assessing the Impact of Discharges of Radioactive Substance to the Environment
,” Safety Reports Series No.19, Vienna, Austria.
10.
U.S. Nuclear Regulatory Commission
, 1977, “
Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50
,” RG1.109, Washington, DC.
11.
Health and Safety Executive
, 2006,
Safety Assessment Principles for Nuclear Facilities
, London, UK.
12.
International Commission on Radiological Protection
, 1993, “
Protection From Potential Exposure: A Conceptual Framework
,”
Annals of the ICRP, ICRP Publication 64
,
Pergamon
,
Oxford, UK
, Vol.
23
.
13.
International Atomic Energy Agency
, 2006, “
Decommissioning of Facilities Using Radioactive Material
,” IAEA Safety Standards Series No. WS-R-5, Vienna, Austria.
14.
International Atomic Energy Agency
, 1999, “
Decommissioning of Nuclear Power Plants and Research Reactors
,” Safety Standards Series No. WS-G-2.1, Vienna, Austria.
15.
OECD Nuclear Energy Agency
, 2002,
The Decommissioning and Dismantling of Nuclear Facility—Status, Approaches, Challenges
, Issy-les-Moulineaux, France.
16.
OECD Nuclear Energy Agency
, 2008,
Regulating the Decommissioning of Nuclear Facilities
, Issy-les-Moulineaux, France.
You do not currently have access to this content.