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- W14884095 abstract "The HTGR utilizes thorium as the fertile material and fully enriched uranium as the makeup feed material. The bred U-233 is recovered and continuously recycled. The discharged feed material is recovered and recycled once more through the reactor before being permanently retired. The bred U-233 is a valuable fuel and its intrinsic neutronic worth, i.e., parity is 1.43 times the value of fully enriched U-235. Parasitic neutron absorptions in U-236 are significant and are proportional to the product of the in-core U-236 inventory and the effective cross section of U-236. The reference recycle mode of operation limits the U-236 inventory buildup and minimizes the effective cross section of U-236. The U-236 that gradually builds up in the bred uranium is unshielded and its neutronic parity is typically -0.58 the value of fully enriched U-235. The U-236 produced in the feed uranium elements and recycled once more is heavily shielded and has a value of -0.20 to -0.25 the value of fully enriched U-235. (auth)" @default.
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- W14884095 date "1975-11-01" @default.
- W14884095 modified "2023-09-27" @default.
- W14884095 title "Neutronic values of U-233 and U-236 in the HTGR" @default.
- W14884095 doi "https://doi.org/10.2172/4089241" @default.
- W14884095 hasPublicationYear "1975" @default.
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