[ RadSafe ] BWR radiation safety issues

[bjmannpe at aol.com]

Jeffry:

tion to the references identified by the other responders, here are a few good references on radionuclide production (from fuel and corrosoin products) ransport and measurement in light water reactor systems. These are texts or monographs (as opposed to papers in technical publications):

1. Cohen, Water Coolant Technology of Power Reactors, American Nuclear Society, 1985. This is a good introduction and summary of what was known through the early 80's. May be out of print.

2. Neeb. Radiochemistry of Nuclear Power Plants with Light Water Reactors, Walter deGruyter, Berlin 1997. Comprehensive, but very expensive - may be available from a library.

3. Lin, Radiochemistry in Nuclear Power Reactors, National Academies Press 1996.

Other good sources of information are:

various EPRI reports such as BWR Water Chemistry Guidelines and Operating experience reports. Requires an entree with EPRI, however.

BWR Owners Group, again an entree is needed.

Bruce Mann






-----Original Message-----
From: Kulp, Jeffrey B <kulpjb at wsu.edu>
To: The International Radiation Protection (Health Physics) Mailing List <radsafe at agni.phys.iit.edu>
Sent: Mon, Dec 5, 2011 1:41 pm
Subject: [ RadSafe ] BWR radiation safety issues


Hello Radsafers,
I would like to call on the expertise of any HP's who have experience with 
oiling water reactors; I am interested in radiation safety issues associated 
ith boiling water reactors while operating and shutdown. My interest is 
rimarily in the steam, condensate and feed systems. I know about N-16 carryover 
o the steam side of the plant, but I read an article recently that discusses 
roblems with Xe, Kr, and Iodine as well; these are fission products, are the 
uthors saying that the fuel cladding is not able to contain fission product 
ases? Another article I read talks about activated corrosion products in the 
ondensate and feed systems. How do the corrosion products become activated, is 
he condensate and feed systems in a BWR plant subject to a neutron flux? Any 
larification offered will be appreciated.
Thanks,
Jeff Kulp
ashington State University
adiation Safety Office
ullman, WA 99164-1302
509) 335-8175
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