Fission Products Release from Irradiated FBR MOX Fuel during Transient Conditions

Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior

“…Gamma-ray spectra were measured continuously by a gamma-ray spectrometer of the filter set during the heating test. Other details of the apparatus are found in the literature [30].…”

“…This apparatus was originally developed for the evaluation of the FP release behavior of irradiated MOX fuels for fast reactors and many fundamental findings were accumulated in heating tests of oxide and nitride fuels [30][31][32][33] irradiated in the experimental fast reactor Joyo. This apparatus is equipped with a high-frequency induction furnace, solid FP sampling systems, a fission gas sampling system, gas analysis equipment and a gamma-ray spectrometer [30]. Only the irradiated fuel pellets (without cladding) are put into a tungsten (W) crucible, then loaded into the induction furnace.…”

“…The heating test was performed using an FP release behavior test apparatus [30]. This apparatus was originally developed for the evaluation of the FP release behavior of irradiated MOX fuels for fast reactors and many fundamental findings were accumulated in heating tests of oxide and nitride fuels [30][31][32][33] irradiated in the experimental fast reactor Joyo.…”

Compound Process Fuel Cycle Concept and Core Characteristics

“…5.1 3) under the conditions of 1,673 K and 0.1 MPa with initial condition data taken from irradiated FBR MOX fuel, 4) are presented in Table 1. Removal rates for the FPs not described in Table 1 are assumed to be zero, implying that those FPs are recycled with trans uranium (TRU) nuclides in this concept.…”

Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy – low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris

“…TEPCO is planning to survey the inside of the containment vessel in its mid-to long-term road map for decontamination of 1F, which would reveal the characteristics of the fuel debris and the step-by-step accident sequence would be understood. Here, on the basis of the data from the TMI-2 fuel debris and follow-up experiments worldwide [21][22][23][24], the volatility is defined and categorized by the release fraction from fuel material, and the following FP release fractions are assumed in the present paper: up to ∼100% for volatile FPs such as cesium (Cs) and iodine (I); 10%∼50% for low-to medium-volatile FPs such as ruthenium (Ru) and antimony (Sb), which tend to be largely absent from the oxide melt phase but are found concentrated in metallic stringers; and 0% to several per cent for low-to non-volatile FPs such as lanthanides (Ln) and zirconium (Zr), which are generally stable in the oxide melt phase but could be influenced by high temperature and the atmospheric conditions. Even with a large release fraction of Cs, the ratio of 134 Cs/ 137 Cs has often been used as an index of the burnup in the cleanup of TMI-2 and the Chernobyl Drum Assay System [25] in Chernobyl-4 and other cleanup …”