Create successful ePaper yourself
Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.
<strong>atw</strong> Vol. 62 (<strong>2017</strong>) | Issue 6 ı June<br />
402<br />
DECOMMISSIONING AND WASTE MANAGEMENT<br />
[8] Department of Homeland Security<br />
(2015). Cyber security Framework<br />
Implementation Guidance for U.S.<br />
Nuclear Power Reactors. Available at:<br />
https://www.us-cert.gov/sites/default/<br />
files/c3vp/framework_guidance/<br />
nuclear-framework-implementationguide-2015-508.pdf.<br />
Validation of Spent Nuclear Fuel Nuclide<br />
Composition Data Using Percentage<br />
Differences and Detailed Analysis<br />
Man Cheol Kim<br />
1 Introduction Nuclide composition data of spent nuclear fuels are important in many nuclear engineering<br />
applications. In reactor physics, nuclear reactor design requires the nuclide composition and the corresponding cross<br />
sections. In analyzing the radiological health effects of a severe accident on the public and the environment, the nuclide<br />
composition in the reactor inventory is among the important input data. Nuclide composition data need to be provided<br />
to analyze the possible environmental effects of a spent nuclear fuel repository. They will also be the basis for identifying<br />
the origin of unidentified spent nuclear fuels or radioactive materials.<br />
The Spent Fuel Isotopic Composition<br />
(SFCOMPO) database [1–3], which<br />
was originally developed by the Japan<br />
Atomic Energy Research Institute and<br />
is now managed by the Organization<br />
for Economic Co-operation and Development/Nuclear<br />
Energy Agency (OECD/<br />
NEA), provides measured nuclide composition<br />
data of spent nuclear fuels.<br />
The SFCOMPO database has been<br />
widely used to validate computer codes<br />
and nuclear data libraries for spent<br />
fuel and fuel cycle applications. For<br />
example, Lee [4] validated TR4PEP, a<br />
depletion code combining the continuous-energy<br />
Monte Carlo transport<br />
code TRIPOLI-4.3 and the point<br />
depletion code PEPIN-2, using the<br />
Takahama-3 post-irradiation examination<br />
results provided in the SFCOMPO<br />
database. Fast et al. [5] compared the<br />
code calculation results obtained using<br />
SCALE 6.0 and 6.1 with measurement<br />
data from Obrigheim nuclear power<br />
plant (NPP) to investigate the validity<br />
of the correlations for burnup calculations<br />
involving key nuclides such as<br />
Cs-134, Cs-137, and Eu-154. Nicolaou<br />
[6] tested the potential of isotopic<br />
fingerprinting for nuclear forensics<br />
purposes using the measurement data<br />
provided in the SFCOMPO database.<br />
With the recognition of the importance<br />
of extending the SFCOMPO<br />
database, the Expert Group on<br />
Assay Data of Spent Nuclear Fuel<br />
Authors<br />
Sébastien Champigny<br />
MBA, Dipl.-Phys., M.Eng.<br />
Product manager cyber security for<br />
critical infrastructures<br />
Deeksha Gupta<br />
M.Sc. in Nuclear Sci. & Tech.<br />
Cyber security PhD Candidate<br />
(EGADSNF), which is in charge of<br />
main taining the OECD/NEA SFCOMPO<br />
database, is trying to obtain new assay<br />
data that are not open to the public or<br />
are open but not widely available.<br />
Suyama et al. [7] mentioned that the<br />
use of the OECD/NEA framework was<br />
intended to facilitate the collection of<br />
new data from member countries.<br />
Possible candidates for newly added<br />
data are summarized in Gauld and<br />
Rugama [8] and the state-of-the-art<br />
report by EGADSNF [9]. For this<br />
purpose, Suyama et al. [10] provided<br />
additional measurement data from<br />
Ohi-1 and Ohi-2 with detailed information<br />
and specifications so that they can<br />
be added to the SFCOMPO database.<br />
Raap et al. [11] reported on the expansion<br />
of the SFCOMPO database by<br />
the addition of measured data from<br />
CANDU reactors, MAGNOX reactors,<br />
VVERs, and RBMKs for use in developing<br />
isotopic signatures for nuclear<br />
forensics purposes.<br />
As the EGADSNF admitted in the<br />
state-of-the-art report [9], measurement<br />
data were added to the SFCOMPO<br />
database as reported by laboratories,<br />
without peer review. Validation of<br />
the data to assess the quality of the<br />
measurements is con sidered a priority<br />
task for improvement of the SFCOMPO<br />
database. The measurement data in<br />
the SFCOMPO database have been<br />
validated in several recent studies.<br />
Venesa Watson<br />
Master in Computer Forensics<br />
Cyber security PhD Candidate<br />
Dr. Karl Waedt<br />
Senior expert Cyber Security<br />
Concepts & Architecture<br />
AREVA GmbH<br />
Paul-Gossen-Straße 100<br />
91052 Erlangen, Germany<br />
Gauld et al. [12] described the recent<br />
experience of Oak Ridge National<br />
Laboratory in validating the measured<br />
isotopic composition data of spent<br />
nuclear fuel. Among the 118 PWR<br />
experimental assay data, 87 (73.7 %)<br />
were from the SFCOMPO database.<br />
Gauld et al. [12] reported problems<br />
such as highly erratic Am-241<br />
measurement data from Takahama-3<br />
due to possible errors in the adjustment<br />
of the time of discharge and<br />
physically impossible measurement<br />
results due to possible typographical<br />
errors. However, the details on how the<br />
SFCOMPO database should be revised<br />
are not clearly described. Okumura et<br />
al. [13] described how the measurements<br />
of Se-79, Tc-99, Sn-126, and<br />
Cs-135 for the Cooper, Calvert Cliffs-1,<br />
and H. B. Robinson-2 reactors in the<br />
SFCOMPO database should be revised<br />
by applying the latest nuclear data,<br />
especially the half-lives of the four<br />
nuclides. For example, the calculatedto-experimental<br />
value for Se-79<br />
changed from 5.5 to 0.92 after the<br />
application of the latest half-life of<br />
Se-79 provided by Bienvenu et al. [14].<br />
This paper proposes a simple<br />
method for analysis and validation of<br />
nuclide composition data of spent<br />
nuclear fuels such as those found in<br />
the SFCOMPO database. The proposed<br />
method consists of a simplified<br />
code calculation, the assumption of a<br />
Decommissioning and Waste Management<br />
Validation of Spent Nuclear Fuel Nuclide Composition Data Using Percentage Differences and Detailed Analysis ı Man Cheol Kim