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Management of Commercially Generated Radioactive Waste - U.S. ...

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Comment<br />

Number<br />

2-17<br />

Comment<br />

Number<br />

also be evaluated The should therefore be 5 x 10- 7 also be evaluated. The description <strong>of</strong> severe accidents in Table 6.2.6<br />

f / es pin e it in t<br />

. Table B.2 <strong>of</strong> PNL-2588 shows a release fraction<br />

<strong>of</strong> 2 x 10<br />

5 <strong>of</strong> 00E/ET-0028 indicates a small opening will exist in the cask.<br />

for actinides and other fission products. Note that both <strong>of</strong><br />

these release fractions are for accident scenarios that involve creep rupture<br />

Accident n number r 6<br />

6.2.8<br />

8 is<br />

is based<br />

b d o n 2<br />

on number 6.2.7. Number 6.2.8 assumes that<br />

no emergency action is taken to cool the cask involved in the 6.2.7 accident.<br />

This results in 50% <strong>of</strong> the fuel rods being perforated in number 6.2.8be<br />

in numbe 8 6<br />

instead <strong>of</strong> only 1% being perforated in number 6.2.7, in addition to 100%<br />

<strong>of</strong> f the oolantbeing coolant being released in<br />

in both<br />

both accidents,<br />

accidents. Thus, release fractions<br />

<strong>of</strong> fuel rod cladding. Since in accident number 6.2.8 it is assumed that<br />

50% <strong>of</strong> the rods fail the release fraction for actinides and other fission<br />

produ oud x -5 if te re t <strong>of</strong> are sed e<br />

1 x 10 if the results <strong>of</strong> PNL-2588 are used. Recommend<br />

the basis for the release fractions used in DOE/ET-0028 be reexamined and<br />

e bais for te release fractions used in O 0 be reemed<br />

any discrepancies with the fractions used in the PNL study be resolved.<br />

in number 8 6.2.8 should be 50 times higher than in number 6.2.7.<br />

n nber 2.8<br />

Indeed<br />

hould be 50 te higher than in numr 6.2.7. Indeed. The following discussion shows that the<br />

85<br />

amount <strong>of</strong> Kr 85 or Kr<br />

released for accident<br />

8 5 , 12, and H the release<br />

fmor<br />

fractions<br />

Kr<br />

given are 50 times higher for ..<br />

8 , the r f s g a 5 t h o<br />

number 6.2.8 than for 6.2.7. However, although mixed fission products and<br />

number 6.2.8, the most severe accidept, has been underestimated. Table<br />

6.2.7 <strong>of</strong> E/ET-028 indicates that 30% <strong>of</strong> the Kr 85 actinides are reportedly released in number 6.2.7, only Cs134 and Cs<br />

will exist in fuel rod<br />

137 are<br />

reported as being released reort in n as n number n r r<br />

6.2.8.<br />

a<br />

This can also be seen in Tables<br />

4.1.1-10 and 4.1.1-12 <strong>of</strong> DOE/ET-0029 which gives the actual number <strong>of</strong> curiesperforated<br />

released. Note<br />

TOOE/ET-028<br />

that Table 4.1.1-10 gives the curies released for accident<br />

number numhor f 6.2.6, ) 6 Kt a moderate accident a in which only 5% <strong>of</strong> the cavity coolant is<br />

released and only 0.25% <strong>of</strong> the fuel rods exhibit cladding.failure. The table<br />

show fission products such as 90 95 inper<br />

Sfisio r such a r<br />

void spaces. Accident number 6.2.8 assumes that 50% <strong>of</strong> the fuel rods are<br />

perforated so that the release fraction reported in Table 6.2.6 <strong>of</strong><br />

so that the ease fracion rpoted in Table cask inv<br />

is 0.15. This table also indicates that the cask inventory<br />

g i Table 3 o e se eteinngt<br />

given in Table 3.3.8 <strong>of</strong> OE/ET-0028 should be used for determining the<br />

actual number <strong>of</strong> curies released. Table 3.3.8 indicate 9.5 x I03 curies<br />

in<br />

MTHM. Since Table 6.2.6 indicates that a cask will contain 4 MTHM, c"<br />

9<br />

and Nb 95 and the actinides such as this means a total inventory <strong>of</strong> 38 x 10 3 curies <strong>of</strong> Kr 85 Pu<br />

. With a release<br />

239 and Cm being released. Table 4.1.1-12, which lists the radionuclides<br />

released for accident number 6.2.8, the severe accident, does not contain<br />

fraction <strong>of</strong> 0.15, this results in 5.7 x 103 curies <strong>of</strong> Kr85 being released.<br />

Table 4.1.1-12 <strong>of</strong> DOE/ET-0029 shows only 5.3 x 10 curies <strong>of</strong> Kr5 being<br />

any <strong>of</strong> the additional fission products or actinides listed for the less<br />

severe accident. Is this simply an oversight or is the contribution to the released.<br />

dose from these nuclides negligible compared to the dose resulting from<br />

the nuclides that are listed?<br />

Paragraph 3: Some discussion should be included describing the composition<br />

<strong>of</strong> a special train and the advantages and disadvantages resulting from its<br />

A study conducted by Battelle's Pacific Northwest Laboratory, "An Assessment <strong>of</strong> a special train and the advantages and disadvantages resulting from its<br />

use. Is it a safer mode <strong>of</strong> transport? Does it have better safeguard<br />

<strong>of</strong> the Risk <strong>of</strong> Transporting Spent Nuclear Fuel by Truck," PNL-2588 uses use s t a safer e f trasrt es t ae etter safeuar<br />

release fractions for actinides and fission products other than gases that features?<br />

are significantly higher than those derived from the accidents describedd.25 p.<br />

in E/ET-0028. As previously shown the release fractions for actinides Line 23: Can an aerial radiation survey detect a spent fuel cask that has<br />

and mixed fission products in accident number 6.2.8 should be 50 times higher not been breached and is located inside a building?<br />

than those used in accident number 6.2.7. Table 6.2.6 <strong>of</strong> DOE/ET-0028 shows<br />

a release fraction <strong>of</strong> 1 x 10 "8 for actinides and mixed fission products for<br />

accident number 6.2.7. The release fraction for accident number 6.2.8<br />

2-18

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