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Title: Assembly-level calculations for transuranics recycling in pressurized water reactors

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6912430
;  [1]
  1. Univ. of Michigan, Ann Arbor, MI (United States)

In this paper, we present fuel depletion calculations evaluating the feasibility and efficiency of transmuting transuranics (TRUs) from spent nuclear fuel in pressurized water reactors (PWRs). In contrast to previous studies, which focused on plutonium recycling, we consider recycling all TRUS, including neptunium, americium, and curium isotopes. Single-assembly and (2 x 2) color-set calculations have been performed with the CASMO assembly-level collision probability code to model equilibrium PWR configurations. There has been renewed interest in the separation and transmutation of TRUs for reducing the long-term radioactivity in spent-fuel repositories. With low capture-to-fission ratios for TRUs in a fast spectrum, liquid-metal reactors (LMRS) are often considered favorable for transmutation of TRUS. The TRU fission cross sections are, however, larger in a thermal spectrum, which offers the potential for thermal transmutors to operate with a smaller TRU inventory, resulting in a higher fractional depletion rate and a higher TRU inventory reduction (TIR) factor. The TIR factor is defined as the ratio of the TRU inventory, without the TRU transmutor, to the inventory that would accumulate with TRU reprocessing and recycling. We present a preliminary study on how standard PWR designs could realize these potential advantages of thermal spectrum reactors.

OSTI ID:
6912430
Report Number(s):
CONF-931160-; CODEN: TANSAO
Journal Information:
Transactions of the American Nuclear Society; (United States), Vol. 69; Conference: American Nuclear Society (ANS) winter meeting, San Francisco, CA (United States), 14-18 Nov 1993; ISSN 0003-018X
Country of Publication:
United States
Language:
English