2003
DOI: 10.1016/s0022-3115(03)00147-8
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Core burnup calculation and accidents analyses of a pressurized water reactor partially loaded with rock-like oxide fuel

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Cited by 7 publications
(9 citation statements)
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“…Figure 7 shows the change where 239 Pu decreases by about 90% [3]. The NMB code considering burn-up dependency of cross section can reasonably reproduce a result of the SRAC code [8] with error less than 10%, as shown in Figure 8.…”
Section: Theory and Validation Of Burn-up Calculationmentioning
confidence: 70%
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“…Figure 7 shows the change where 239 Pu decreases by about 90% [3]. The NMB code considering burn-up dependency of cross section can reasonably reproduce a result of the SRAC code [8] with error less than 10%, as shown in Figure 8.…”
Section: Theory and Validation Of Burn-up Calculationmentioning
confidence: 70%
“…Instead of MOX fuel, rocklike oxide (ROX) fuel has been developed for the purpose of achieving better stability of SF and higher transmutation of fissionable Pu than MOX fuel [2]. ROX fuel contains mainly Pu with less amount of 238 U to reduce Pu production and to transmute about 90% of fissile Pu [3,4]. ROX SF is chemically stable so radionuclides can be confined in a repository, and it is difficult to obtain Pu by reprocessing.…”
Section: Introductionmentioning
confidence: 99%
“…By modifying the assembly design of ROX and addition of Er burnable poison, the total power peaking factor could be reduced to as low as 1.7 [18], that is small enough to keep the fuel temperature lower than 1700 K, when the average linear heat rate of 18 kW m À1 is assumed [18]. In that ROX-PWR core, it is possible to suppress the maximum linear heat rate to 31 kW m À1 .…”
Section: Microstructurementioning
confidence: 99%
“…Out-of pile irradiation studies designed to understand the mechanism of radiation damage have been completed [6]. Neutronic feasibility of YSZ-based IMF has been also assessed [7] complemented by core burnup calculations and accident analyses [8]. Despite its excellent radiation resistance, compatibility with reactor materials and good neutronic properties, low thermal conductivity is the main disadvantage of YSZ.…”
Section: Introductionmentioning
confidence: 99%