Re: japan doses

["Tosh Ushino" <tushino@icnpharm.com>]

Jim,

I *thought* I had posted this information on RADSAFE few days ago but apparently
I had some email failure.  I'll try again since I can find no record of it.
Please excuse me if this is a repeat. I also sent a reply to Bjorn Cedervall
privately yesterday.

There is no information on Science and Technology web site on how the dose to
the three workers was determined. However, the web page does contain tables of
other plant workers, fire fighters and local residents who were whole body
counted for Na-24. Neutron dose was calculated from the Na-24 activity. I don't
know how gamma dose contribution was calculated (probably ratioed). Total dose
due to neutron and gamma is given.

Personnel radiological data can be found at:
JCO workers:   http://www.sta.go.jp/genan/jco/jco91007_5a.html
Fire fighters: http://www.sta.go.jp/genan/jco/jco91007_5b.gif
Area Residents:     http://www.sta.go.jp/genan/jco/jco91007_5c.gif

The tables are arranged as follows starting from left column,
time of intiation of accident,
measurement start time,
elapsed time,
internal Na-24 activity (measured with whole body counter)
corrected Na-24 activity
external contamination level (most below detectable level, contamination mostly
on head, one contaminated left shoe on worker #8)
calculated dose (neutron plus gamma) in mGy

Also, check out these: Map of gamma & neutron monitoring locations around JCO:

http://www.sta.go.jp/genan/jco/jco91007_5h.gif
http://www.sta.go.jp/genan/jco/jco91007_5i.gif

One of the tables in Japanese section stated that neutron dose rate were
measured using "rem counter" and NaI detector
used for gamma.

Tosh Ushino
ICN Dosimetry
tushino@icnpharm.com





Jim Muckerheide <jmuckerheide@delphi.com> on 10/13/99 11:27:13 AM

Please respond to radsafe@romulus.ehs.uiuc.edu

To:   Multiple recipients of list <radsafe@romulus.ehs.uiuc.edu>
cc:    (bcc: Tosh Ushino/HQ/ICN)

Subject:  Re: japan doses



The doses have been so reported for a week or so. But it seems to me the
question is: "How were these doses determined?" That seems not to have
been addressed anywhere. Calculated? measured? biological response?

Originally there was also a lot of discussion of whether "the doses"
should be being reported in Gy or Sv, but not really what RBE for
neutrons is (should be) applied to distinguish a dose in Gy vs. Sv.
(Neutron spectrum?)

Does anyone have info? an idea?

Regards, Jim Muckerheide
========================

James Deye wrote:
>
> In answer to the question about doses in the Japan accident.
> This week's issue of Science (vol 286) #8 pp 209 states that the higest
> exposed individual received 17 Sv while the second person got 10 Sv  and the
> third 3 Sv. In all "three workers were hospitalized and more than 60 others,
> including three rescue workers and seven golfers on a neighboring course,
> were found to have been exposed to high levels od radiation." A new therapy
> using stem cells is being tried in place of bone marrow transplants.
> J. Deye
>
>         ***********     ************
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