“…CE NFH includes CEAs and NSAs. Similar information is provided for irradiated BWR control blades, which are considered Greater-Than-Class-C radioactive waste [65].…”
Section: Nfh Physical Characteristics and Operating Conditionsmentioning
confidence: 99%
“…The irradiation history of a spent RCCA, discharged after 12 cycles and 102,767 h of service from the WE PWR Point Beach 1 power reactor, is provided in the PNL-10103 report [65]. Table 50 provides the cycle burnup values of the host assemblies.…”
Section: Cra Rcca and Cea Design Datamentioning
confidence: 99%
“…The irradiation history of a GE control blade discharged from the Duane Arnold power reactor is provided in the PNL-10103 report [65]. This blade was used during 10 operation cycles at two reactor core locations.…”
Section: Bwr Control Blade Exposure Limitsmentioning
confidence: 99%
“…The insertion data presented in Table 56 were extracted from the graphs available in the PNL-10103 report and might be imprecise. The neutron exposure during full insertion is extremely low because the reactor was either coasting down or at the zero-power level [65]. 60 Co measurements on samples taken at various axial locations along the blade were ~ 2,000 g/g for the handle and tip and an approximately uniform 1,200 g/g for the sheath.…”
Section: Bwr Control Blade Exposure Limitsmentioning
confidence: 99%
“…BPRAs are typically removed after one irradiation cycle. The burnup reported in the PNL-10103 report [65] for a spent BPRA discharged from the WE PWR Point Beach 1 power reactor is ~16,500 MWd/MTU. However, the burnup of a fuel assembly in modern PWR cores is much higher (e.g., 28.8 GWd/MTU in a 24-month cycle [69]).…”
“…CE NFH includes CEAs and NSAs. Similar information is provided for irradiated BWR control blades, which are considered Greater-Than-Class-C radioactive waste [65].…”
Section: Nfh Physical Characteristics and Operating Conditionsmentioning
confidence: 99%
“…The irradiation history of a spent RCCA, discharged after 12 cycles and 102,767 h of service from the WE PWR Point Beach 1 power reactor, is provided in the PNL-10103 report [65]. Table 50 provides the cycle burnup values of the host assemblies.…”
Section: Cra Rcca and Cea Design Datamentioning
confidence: 99%
“…The irradiation history of a GE control blade discharged from the Duane Arnold power reactor is provided in the PNL-10103 report [65]. This blade was used during 10 operation cycles at two reactor core locations.…”
Section: Bwr Control Blade Exposure Limitsmentioning
confidence: 99%
“…The insertion data presented in Table 56 were extracted from the graphs available in the PNL-10103 report and might be imprecise. The neutron exposure during full insertion is extremely low because the reactor was either coasting down or at the zero-power level [65]. 60 Co measurements on samples taken at various axial locations along the blade were ~ 2,000 g/g for the handle and tip and an approximately uniform 1,200 g/g for the sheath.…”
Section: Bwr Control Blade Exposure Limitsmentioning
confidence: 99%
“…BPRAs are typically removed after one irradiation cycle. The burnup reported in the PNL-10103 report [65] for a spent BPRA discharged from the WE PWR Point Beach 1 power reactor is ~16,500 MWd/MTU. However, the burnup of a fuel assembly in modern PWR cores is much higher (e.g., 28.8 GWd/MTU in a 24-month cycle [69]).…”
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.