Physical and decay characteristics of commercial LWR spent fuel

Abstract

Schematic of a typical Westinghouse fuel rod. 2-13 Schematic of a typical Westinghouse fuel assembly* 2-14 Schematic of VANTAGE 5 fuel assembly. 2-15 Schematic of a fuel rod from St. Lucie Plant-1-2-16 14 X 14 array. 2.5 Schematic of a fuel assembly from St. Lucie 2-17 Plant-1-14 X 14 array. 2.6 Schematic of a fuel rod from Arkansas Nuclear One, 2-18 Unit 2-16 X 16 array. 2.7 Schematic of a fuel assembly for Arkansas Nuclear (toe, 2-19 Unit-2-16 X 16 array. 2.8 Babcock and Wilcox fuel rod. 2-20 2.9 Babcock and Wilcox fuel assembly. 2-21 2.10 Typical General Electric fuel rod and assembly. 2-22 2.11 Cutaway diagram of an 8 x 8 General Electric fuel 2-23 assembly. 2.12 Cutaway diagram of QUAIH-fuel assembly. 2-24 2.13 Cutaway diagram of a partial QUAIH-fuel ass^nbly 2-25 showing internals. 2.14 Cutaway diagram of QUAIH-fuel channel. 2-26 2.15 Cutaway diagram of a QUAD-t-fuel assembly with 2-27 partially removed minibundle. 2.16 Cutaway diagram of a QUAIH-fuel minibundle. 2-28 3.1 Radioactivity produced by 1 metric ton of initial 3-7 heavy metal: PWR; 60,000 MWd. 3.2 Radioactivity produced by 1 metric ton of initial 3-8 heavy metal: PWR; 33,000 MWd. 3.3 Radioactivity produced by 1 metric ton of initial 3-9 heavy metal: BWR; 40,000 MWd. 3.4 Radioactivity produced by 1 metric ton of initial 3-10 heavy metal: BWR; 27,500 MWd. C.l Data collection pathway for spent fuel characteristics C.2 Calculational pathway for 0RIGEN2-generated data. C.3 Construction pathway for the nuclear waste characteristics data base. XI LIST OF TABLES (continued) Table Page 3.17 Variation in neutron production (neutrons/s«MTIHli| ^ 3-40 spontaneous fission as a function of time since discharge from a 60,000-MWd/MTIHM PWR 3.18 Variation in neutron production (neutrons/S'MTIHM) by 3-40 spontaneous fission as a function of time since discharge from a 33,000-MWd/MTIHM PWR 3.19 Variation in neutron production (neutrons/s'MTIHM) by 3-41 spontaneous fission as a function of time since discharge from a 40,000-MWd/MTIHM BWR 3.20 Variation in neutron production (neutrons/s'MTIHM) by 3-41 spontaneous fission as a function of time since discharge from a 27,500-MWd/MTIHM BWR 3.21 Variation in neutron production (neutrons/s'MTIHM) by 3-42 the alpha-neutron reaction as a function of time since discharge from a 60,000-MWd/MTIHM PWR 3.22 Variation in neutron production (neutrons/s'MTIHM) by 3-43 the alpha-neutron reaction as a function of time since. discharge from a 33,000-MWd/MTIHM PWR 3.23 Variation in neutron production (neutrons/s'MTIHM) by 3-44 the alpha-neutron reaction as a function of time since discharge from a 40,000-MWd/MTIHM BWR 3.24 Variation in neutron production (neutrons/s'MTIHM) by 3-45 the alpha-neutron reaction as a function of time since discharge from a 27,500-MWd/MTIHM BWR 3.25 Variation in photon production (photons/s»MTIHM) as a 3-46 function of time since discharge from a 60,000-MWd/MTIHM PWR 3.26 Variation in photon production (photons/s'MTIHM) as a 3-47 function of time since discharge from a 33,000-MWd/MTIHM PWR 3.27 Variation in p...

TSPA 1991: An initial total-system performance assessment for Yucca Mountain; Yucca Mountain Site Characterization Project

“…The data in Table 4-1 were taken from Wilson (1991). The data sources are given in Wilson's report, but the principal _mrce is Roddy et al (1986). The inventories follow from the as- The 60/40 distribution of PWR and BWR spent fuel follows from data in the SCP;…”

“…Table 5-1 could be high. Van Konynenburg (1991) re-examined the assumptions of Roddy et al (1986) regarding 14C production during reactor operation, and he suggested the following revised inventory numbers Aside from tile gaseous nature of the 14C releases, tile other major difference between 14C releases and releases of the other nuclides being modeled (see Table 4-1)…”

“…These amounts are listed according to type of reactor (BWR or PWR) and amount of burnup (in MWd/MTHM). To determine the isotopic composition of these inventories at the year 2040, the decay of the radioisotopes from time of discharge from the reactor to the year 2040 is calculated using the ORIGEN computer code (Roddy et al, 1986). The inventories are then lumped into roughly 10-year intervals.…”

“…For example, suppose an element has a solubility limit of 1 and there are two isotopes, in the ratio of 60 percent isotope A Table 4-1, the only ones for which partitioning is of concern are 234U, 239plJ v and 243Am (note that partitioning is not an issue for the alteration-limited nuclides because it is assumed that their solubility is high enough that it is not a factor). From Roddy et al (1986), the amounts of all isotopes of those three elements at 100 yr and at 10,000 yr were obtained. At 100 yr, 2_U makes up about 0.028 percent of the uranium (by rnoles), 239pu makes up about 64 percent of the plutonium, and 243Am makes up about 0.72 percent of the americium.…”

Review of radionuclide source terms used for performance-assessment analyses; Yucca Mountain Site Characterization Project

“…For gas-flow analyses, only CO2 transport was considered, so only 14C was used in that source. Because direct release was assumed to occur by mechanical means, ali radionuclides listed in Table 1 (Roddy et al, 1986). This database provides activities for radionuclides as a function of decay, burnup, and reactor type.…”