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Title: Neutronic values of U-233 and U-236 in the HTGR

Technical Report ·
DOI:https://doi.org/10.2172/4089241· OSTI ID:4089241

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)

Research Organization:
General Atomics, San Diego, CA (United States)
DOE Contract Number:
E(04-3)-167
NSA Number:
NSA-33-019450
OSTI ID:
4089241
Report Number(s):
GA-A-13728
Resource Relation:
Other Information: Orig. Receipt Date: 30-JUN-76
Country of Publication:
United States
Language:
English