[논문]SHIELDED LASER ABLATION ICP-MS SYSTEM FOR THE CHARACTERIZATION OF HIGH BURNUP FUEL

Ha, Yeong-Keong; Han, Sun-Ho; Kim, Hyun-Gyum; Kim, Won-Ho; Jee, Kwang-Yong

doi:10.5516/net.2008.40.4.311

SHIELDED LASER ABLATION ICP-MS SYSTEM FOR THE CHARACTERIZATION OF HIGH BURNUP FUEL 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.40 no.4, 2008년, pp.311 - 318

Ha, Yeong-Keong (Korea Atomic Energy Research Institute) , Han, Sun-Ho (Korea Atomic Energy Research Institute) , Kim, Hyun-Gyum (Korea Atomic Energy Research Institute) , Kim, Won-Ho (Korea Atomic Energy Research Institute) , Jee, Kwang-Yong (Korea Atomic Energy Research Institute)

Abstract ▼ AI-Helper

In modem power reactors, nuclear fuels have recently reached 55,000 MWd/MtU from the initial average burnup of 35,000 MWd/MtU to reduce the fuel cycle cost and waste volume. At such high burnups, a fuel pellet produces fission products proportional to the burnup and creates a typical high burnup structure around the periphery region of the pellet, producing the so called 'rim effect'. This rim region of a highly burnt fuel is known to be ca. $200\;{\mu}m$ in width and is known to affect the fuel integrity. To characterize the local burnup in the rim region, solid sampling in the micro meter region by laser ablation is needed so that the distribution of isotopes can be determined by ICP-MS. For this procedure, special radiation shielding is required for personnel safety. In this study, we installed a radiation shielded laser ablation ICP-MS system, and a performance test of the developed system was conducted to evaluate the safe operation of instruments.

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제안 방법

Thus, for the direct analysis of the isotopes and their radial distribution in a spent fuel, we developed a radiation shielded laser ablation ICP-MS system [8-10]. The performance of this system was tested, and an analysis of the isotopic ratio in a simulated nuclear fuel (SIMFUEL) was carried out. The goal for this radiation shielded LA-ICP-MS system was to achieve less than 50 gm spatial resolution with less than ±10% standard deviation.
To measure the radial distribution profiles of isotopes in a spent nuclear fuel, a simulated fuel (SIMFUEL) was prepared. Among the fission product elements, Gd was chosen as a dopant because Gd is known to dissolve as a solid solution in UO₂ matrices [14, 15] and to behave as a 'burnable poison'[6, 7, 16].

대상 데이터

For a homogeneous and flat-top-shaped beam profile, Tem0o mode was used. The laser beam was guided onto the sample surface by 90° reflection mirrors and a focusing lens (focal length 60 mm).
The powders of each layer, (UbyGdy)O₂ solid solution in the given range (y=0-0.28), were prepared from U3O8(U content was determined by potentiometric titration) and commercially available Gd2O₃ (Aldri사}, >99.999 %). Calculated amounts of U3O₈ and Gd2O₃ were mixed thoroughly by grinding in an agate mortar to a given composition of a solid solution (Ui-yGdy)O₂ where y ranged from 0 to 0.
To adjust the sampling position and to observe the spot size and its shape, an imaging device composed of a CCD camera (CV-S3200, JAI), a TV tube (OPTEM), an object lens, and an illuminator was installed. The magnification of the viewing optics is x500.

성능/효과

In the performance test, a spatial resolution of better than 50 gm was achieved at less than 55% laser power with 3, 000-3, 500 |im defocusing, which satisfies the target value for this system. Also, a precision of less than ±10% is acceptable for the spent fuel analysis.
The performance of this system was tested, and an analysis of the isotopic ratio in a simulated nuclear fuel (SIMFUEL) was carried out. The goal for this radiation shielded LA-ICP-MS system was to achieve less than 50 gm spatial resolution with less than ±10% standard deviation.

후속연구

Also, a precision of less than ±10% is acceptable for the spent fuel analysis. The measured values of elements forming solid solutions are quite reliable, although further studies are needed for the analysis of various fission products forming met시lie precipitates, insoluble oxides, and volatile elements in a spent fuel. Thus, the shielded LA-ICP-MS constructed in this study can be applicable for producing the databases to interpret local bum up characteristics.

참고문헌 (17)

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