Comparison of Burnup Calculation Results Using Several Evaluated Nuclear Data Files

Suyama, Kenya; Katakura, J.; Kiyosumi, Takehide; KANEKO, Toshiyuki; Nomura, Yasushi

doi:10.1080/18811248.2002.9715160

Cited by 5 publications

(3 citation statements)

References 3 publications

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“…The migrated fission gases form grain boundary bubbles and interlinked tunnels, and finally escape from the pellet. 20) It is shown in Table 1 that the pellet temperatures were above 1000 K at the center and below 900 K at the peripheral of the fuels during the irradiation. Since it has been reported that the boiling point of Cs is 951 K, 11) it is considered that Cs generated in the center region of the pellet behaved like fission gases and a certain fraction migrated through the interlinked tunnels.…”

Section: Release Of Csmentioning

confidence: 98%

“…The error of Cs generation calculated by the SWAT code was evaluated as within 10%. 20) Actual linear heat rates and initial compositions of fuels [12][13][14][15][16][17] were used as inputs. The figure indicates that the generated Cs migrated from the central part of the pellet through the interlinked tunnels and accumulated in the cooler outer region.…”

Section: Release Of Csmentioning

confidence: 99%

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Releases of Cesium and Poorly Volatile Elements from UO₂and MOX Fuels under Severe Accident Conditions

Kudo

Kida

Nakamura

et al. 2007

Journal of Nuclear Science and Technology

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Radionuclide release from fuel under severe accident conditions has been investigated in the VEGA program at the Japan Atomic Energy Agency. In this program, three types of fuel, two UO 2 fuels irradiated at PWR and BWR and a MOX fuel irradiated at the ATR Fugen, were heated up to about 3130 K in helium atmosphere at 0.1 MPa. Comparison of experimental data and evaluation with computer code analyses showed that Cs release is essentially identical among the three fuels. The Cs release from fuel may differ below about 1770 K due to a difference in migration to grain boundaries during irradiation. The difference was not also observed for releases of poorly volatile elements, namely, U, Pu, Sr and Mo between UO 2 and MOX fuels. The release rate of Pu became slightly higher than that of U at 3130 K. The release rate of Sr increased at 3130 K, while that of Mo was quite low at temperatures above 2310 K.

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Section: Release Of Csmentioning

confidence: 98%

Section: Release Of Csmentioning

confidence: 99%

Releases of Cesium and Poorly Volatile Elements from UO₂and MOX Fuels under Severe Accident Conditions

Kudo

Kida

Nakamura

et al. 2007

Journal of Nuclear Science and Technology

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show abstract

“…18,19) The Xe/Kr ratios are calculated based on the assumption that all the fission gases generated were retained in the fuel pellet during base irradiation. Here, the results calculated using the FEMAXI-6 [20][21][22] code, e.g., the amount of retained fission gas atoms in the fuel pellets, were used as inputs for the SWAT code calculation.…”

Section: Code Calculationsmentioning

confidence: 99%

Identification of Radial Position of Fission Gas Release in High-Burnup Fuel Pellets under RIA Conditions

Sasajima

Sugiyama

Chuto

et al. 2010

Journal of Nuclear Science and Technology

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The radial positions of fission gas release (FGR) in high-burnup fuel pellets were examined after pulse irradiations that simulated reactivity-initiated accident (RIA) conditions in the Nuclear Safety Research Reactor (NSRR). The molar ratio of xenon (Xe) to krypton (Kr) (Xe/Kr ratio) in the released gas showed that fission gas was released from the entire region of the pellets of the examined PWR fuels during the pulse irradiations. On the other hand, most fission gas was released from the center and/or intermediate regions of the examined BWR fuel pellets. The analyses of the thermal stress distribution in fuel pellets during the pulse irradiations were carried out by means of a computer code, and the results supported the FGR positions that were estimated from the measured Xe/Kr ratios. Consequently, it is likely that fission gas is not released selectively from the rim structure at the pellet periphery under RIA conditions.

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Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems

Suyama

Murazaki

Ohkubo

et al. 2011

Annals of Nuclear Energy

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Comparison of Burnup Calculation Results Using Several Evaluated Nuclear Data Files

Cited by 5 publications

References 3 publications

Releases of Cesium and Poorly Volatile Elements from UO₂and MOX Fuels under Severe Accident Conditions

Releases of Cesium and Poorly Volatile Elements from UO₂and MOX Fuels under Severe Accident Conditions

Identification of Radial Position of Fission Gas Release in High-Burnup Fuel Pellets under RIA Conditions

Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems

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Comparison of Burnup Calculation Results Using Several Evaluated Nuclear Data Files

Cited by 5 publications

References 3 publications

Releases of Cesium and Poorly Volatile Elements from UO2and MOX Fuels under Severe Accident Conditions

Releases of Cesium and Poorly Volatile Elements from UO2and MOX Fuels under Severe Accident Conditions

Identification of Radial Position of Fission Gas Release in High-Burnup Fuel Pellets under RIA Conditions

Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems

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Releases of Cesium and Poorly Volatile Elements from UO₂and MOX Fuels under Severe Accident Conditions

Releases of Cesium and Poorly Volatile Elements from UO₂and MOX Fuels under Severe Accident Conditions