ML19206B322

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Forwards Estimated Core Inventory of Important Fission & Actinide Products for TMI Reactor
ML19206B322
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/06/1979
From: Kenneke A
NRC OFFICE OF POLICY EVALUATIONS (OPE)
To: Ahearne J
NRC COMMISSION (OCM)
References
NUDOCS 7905090212
Download: ML19206B322 (4)
v • d • e


Text

.

g UNITED STATES E'

NUCLEAR REGULATORY COMMISSION 2-

~

~j W ASHINGTON, D. C. 20S55 9

f

/

April 6, 1979 MEMORANDUM FOR: Commis-1 r Ahearne FROM:

Al "

e, Acting Director, OPE V/

SUBJECT:

ESTIMA7ED ?.CTINIDE AND FISSION PRODUCT INVENTORY AT TMI Attached is the estimated core inventory of important fission and actinide products for the TMI reactor which you asked for.

It is based upon an ORIGEN II computer code run at ORNL yesterday. As you asked, half lives and estimated radioactivity are shown out to 5 years.

Code assumptions are 2.01 percent enrichment; 2,800 MWth; 75 day: full power operation; 210,000 mwd. The detailed fission product data are shown in Attachment 3.

We also obtained some information on the solubility and volatility of the relevant fission products from a radiochemist (Fred Fisher in NMSS) which is shown in Attachment 1.

Then we combined the activity levels according to these chemical properties (see Attachment 2).

After discussion with staff at the site, we have concluded that sufficient data aren't available yet to make it practical to prepare a detailed allocation of nuclides for each of the contaninated plant areas in the charts I gave you yesterday.

However, preliminary estimates from a Bechtel, B&W, and utility group assembled at the site suggests roughly 30 percent of the gaseous fission products may have been released; thus, decay in radioactivity in gases released from the ccre is:*

(Shutdown)

CURIES Assume:

0 day 7 days 1 month 3 months 6 months 1 year 30 percent of gases released (includes I-133) 6.7x107 3.4x107 2.8x106 3.8x104 2.8x104 2.7x104 The same sources suggest 0.1 percent of the other fission products may have been released which should be distributed in the water in RCS, sump water, and the water discharged to the auxiliary building.

Decay of this radioactivity might look like:

  • This contamination could end up in the environment, or containment, auxiliary building or left in RCS.

CONTACT-

-.\\

Dennis Rathbun (OPE) 790 24 634-3295 50907f7 Ted Quay (OPE)

'T 634-3295

Commissioner Ahearne (Shutdown)

CURIES Assume:

O day 7 days 1 month 3 months 6 months 1 year 0.1 percent of non-gaseous fission products released 1.2x107 9.9x105 5.0x105 2.1x105 9.1x104 3.2x104 The assumptions made for release fractions are clearl; tentative, at best. However, the data on core inventory may be useful when coupled with more extensive on-site measurements than has been posssible to date.

For instance, the data here can be ratioed to reflect more accurate release fractions from those assumed here.

Attachments:

As stated cc:

Chairman Hendrie Commissioner Gilinsky Commissioner Kennedy Commissioner Bradford Leonard Bickwit Sam Chilk Lee V. Gossick 24 072

RESIDUAL ACTIVITY AS A FUNCTION OF TIME SINCE THE ACCIDENT CURIES:

@ Residual activity from assumed release of 30 percent gases from the fuel

@ Residual activity from assumed release of 0.1 percent non-gaseous fission products from the fuel hi l

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. Gases:

KR-85, Xe-133, I-131. Most are be trapped in containment.

Some in auxiliary building via water overflow.

Xe-133 may be removed or held up (for decay) via chilled charcoal filter (which also would remove iodine). Warming up filter desorbs gases for storage and disposal in high pressure cylinders.

Partially effective with respect to removal of Kr-85, but the curie level is much lower than Xe and I. (Also Kr-85 requires lower temperatures for effective adsorption.)

. Semi-volatiles:

Cs-134, Cs-137, Ru-103, Ru-106; not much volatilization should be expected here because the temperature has been maintained relatively low.

If the core was uncovered for any period of time, these may have been plated out on the inner surface of the reactor vessel.

. Water solubles:

Cs-134 and Cs-137 (very); Ba-140 and Ba-137 (some);

Sr-90 and Sr-89 (some); Y-90 and Y-91 (some); dissolution into the RCS is largely a leaching-corrosion process * -- and, therefore, depends upon the extent of failed cladding as well as the condition of UO2 pellets in failed fuel.

If fuel damage is severe, these could be transported in particulate form in water if released from the primary

system, in which case they could probably be removed by filtration.

(If in solution, removal by ion exchange is possible.)

. Rare earths: La-140 (limited solubility); Ce-144 and Ce-141 (insoluble);

Pr-143 and Pr-144 (insoluble); No-147 (inso'uble); Pm-147 (insoluble);

it may be expected that these nuclides largely remain in the fuel although trace quantities may plate out in the " cold" portions of the RCS.

  • Other non-volatile fission products: Nb-95 and Zr-95 (very slightly soluable)' chemical and physical behavior similar to rare earths.
  • Substantial corrosion resistance of UO2 pellets is an important design consideration.

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BY CHEF 11 CAL PROPERTIES 3

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Other 1.2x10 1.2x10 1.1x10 7.4x10 3.2x10 5.1x10 1.0x10

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Zr-95 Ru 6.

Actinides 4.0x10 2.6x10" 1.1x10 9.9x10 9.6x10 9.4x10 9.0x10 8.0x10 U, Np, Pu, Am 5

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