07.07.2017 Views

atw 2017-06

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

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!