1977
DOI: 10.2172/7306994
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Assessment of thorium fuel cycles in pressurized water reactors. Final report

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Cited by 16 publications
(2 citation statements)
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“…While standard U-Pu MOX options have been considered (Gul, et al, 2018) (Salam & Hah, 2018) (Alonso, et al, 2018) (Ramirez, et al, 2016) (Haas & Hamilton, 2007) (Cowell & Fisher, 1999) (Schlosser, et al, 1993), studies have shown that Th-Pu MOX may provide a promising alternative (Ernoult, et al, 2015) (Lau, et al, 2014) (Revol, et al, 2013) (National Nuclear Laboratory, 2012 (Fridman & Kliem, 2011) (International Atomic Energy Agency, 2005) (International Atomic Energy Agency, 2002) (Galperin, 1995) (Cadelli & Lippens, 1988) (Shapiro, et al, 1977). The high conversion ratio and lack of breeding of additional Pu in the Th-cycle results in significantly lower Pu / MA content in discharged fuel compared to standard U-Pu MOX, leading to potentially lower levels of radiotoxicity and decay heat of associated waste materials compared to standard UO2 and U-Pu fuels (Hesketh & Thomas, 2013) (International Atomic Energy Agency, 2005).…”
Section: Viable Technologies For Pu Dispositionmentioning
confidence: 99%
“…While standard U-Pu MOX options have been considered (Gul, et al, 2018) (Salam & Hah, 2018) (Alonso, et al, 2018) (Ramirez, et al, 2016) (Haas & Hamilton, 2007) (Cowell & Fisher, 1999) (Schlosser, et al, 1993), studies have shown that Th-Pu MOX may provide a promising alternative (Ernoult, et al, 2015) (Lau, et al, 2014) (Revol, et al, 2013) (National Nuclear Laboratory, 2012 (Fridman & Kliem, 2011) (International Atomic Energy Agency, 2005) (International Atomic Energy Agency, 2002) (Galperin, 1995) (Cadelli & Lippens, 1988) (Shapiro, et al, 1977). The high conversion ratio and lack of breeding of additional Pu in the Th-cycle results in significantly lower Pu / MA content in discharged fuel compared to standard U-Pu MOX, leading to potentially lower levels of radiotoxicity and decay heat of associated waste materials compared to standard UO2 and U-Pu fuels (Hesketh & Thomas, 2013) (International Atomic Energy Agency, 2005).…”
Section: Viable Technologies For Pu Dispositionmentioning
confidence: 99%
“…Two uranium feed isotopic compositions with thorium were studied for intercomparisons: 75-2^ U-233, 21.1^ U-23^, 3.0^ U-235, and 0.7^ U-236, based upon LMFBR thorium fuel equilibrium recycle (FBR U), and 38.0^ U-233, 9.2^ U-23^, 36.5^ U-235, and l6.3^ U-236, based upon PWR discharge uranium from a once-through thorium cycle. 2 The PVfR uranium feed (PWR U) was evaluated to determine the effect on thorium LMFBR performance of U-233 produced in typical LMFBR's. Since there is no stockpile of U-233, a symbiotic LWR-LMFBR system may be necessary for initiation of a LMFBR closed thorium cycle.…”
Section: Mv/e Core Designsmentioning
confidence: 99%