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ASTM Selected Technical Papers
Influence of Radiation on Material Properties: 13th International Symposium (Part II)
By
FA Garner
FA Garner
1
Westinghouse Hanford Company
, P.O. Box 1970, W/A-58,
Richland, WA 99352
;
symposium chairman and editor
.
Search for other works by this author on:
CH Henager, Jr. Jr.
CH Henager, Jr. Jr.
2
Battelle Pacific Northwest Laboratory
, P.O. Box 999, 306/300,
Richland, WA 99352
;
symposium vice-chairman and editor
.
Search for other works by this author on:
N Igata
N Igata
3
University of Tokyo
,
7-3-1 Hongo, Bunkyo-ku, Tokyo 133,
Japan
;
symposium vice-chairman and editor
.
Search for other works by this author on:
ISBN-10:
0-8031-0963-6
ISBN:
978-0-8031-0963-6
No. of Pages:
812
Publisher:
ASTM International
Publication date:
1987

Under contract with the Department of Energy, Rockwell Hanford Operations (Rockwell) conducted a series of studies related to Three Mile Island (TMI) post loss of coolant accident (LOCA) waste handling safety. The key factor in these studies was the control of radiolytic gases, specifically hydrogen and oxygen.

Success was achieved in the prediction of gas generation rates and in the development and application of gas control technologies. That success led to the publication of a “lessons learned” document, providing (1) a step-by-step guide in evaluating potential radiolysis hazards in waste storage and shipment activities and (2) a set of corrective options for preventing or controlling the hazards. The evaluation steps developed in the document are outlined in a functional logic diagram. Several procedures are described which provide safe and effective controls for hydrogen and oxygen levels in containers scheduled for shipment or interim storage. A method is provided to pre-evaluate each control option and select the most cost effective procedure for each case.

1.
Henrie
,
J. O.
and
Appel
,
J. N.
,
Evaluation of Special Safety Issues Associated with Handling the Three Mile Island Unit 2 Core Debris
, RHO-WM-EV-7,
Rockwell Hanford Operations
,
Richland, WA
,
1985
;
also GEND-051,
EG&G Idaho, Inc.
,
Idaho Falls, ID
.
2.
Jordan
,
E. L.
,
Clarification of Conditions for Waste Shipments Subject to Hydrogen Gas Generation
, IN 84-72,
U.S. Nuclear Regulatory Commission
,
Washington, DC
,
1984
.
3.
Henrie
,
J. O.
,
Flesher
,
D. J.
,
Quinn
,
G. J.
, and
Greenberg
,
J.
,
Hydrogen Control in the Handling, Shipping, and Storage of Wet Radioactive Waste
, RHO-WM-EV-9P, Rev. 1,
Rockwell Hanford Operations
,
Richland, WA
,
1986
;
also GEND-052,
EG&G Idaho, Inc.
,
Idaho Falls, ID
.
4.
ASTM
,
Annual Book of ASTM Standards
, Related Standards: E 459-72, E 511-73, E 422-83, E 457-72, E 639-78, C 976-82, and C 518-76,
American Society for Testing and Materials
,
Philadelphia, PA
,
1985
.
5.
Perry
,
J. H.
, Ed.,
Chemical Engineer's Handbook
, 3rd ed.,
McGraw-Hill Book Company
,
New York
,
1950
.
6.
Weast
,
R. C.
, Ed.,
CRC Handbook of Chemistry and Physics
, 48th ed.,
The Chemical Rubber Co.
,
Cleveland, OH
, 1967–1968.
7.
Zabetakis
,
M. G.
,
Flammability Characteristics of Combustible Gases and Vapors
, Bulletin 627, Bureau of Mines,
U.S. Department of the Interior
,
Washington, DC
,
1965
.
8.
Bibler
,
N. E.
,
Radiolytic Gas Production During Long-Term Storage of Nuclear Wastes
, DP-MS-76-51,
E. I. du Pont de Nemours & Co., Savannah River Laboratory
,
Aiken, SC
,
1976
.
9.
Bibler
,
N. E.
,
Gas Production from Alpha Radiolysis of Concrete Containing TRU Incinerator Ash
, Progress Report 2, DPST-78-150-2,
E. I. du Pont de Nemours & Co., Savannah River Laboratory
, Aiken, SC,
1978
.
10.
Bibler
,
N. E.
,
Wallace
,
R. M.
, and
Ebra
,
M. A.
,
Effects of High Radiation Doses on Linde Ion SIV IE-95
, DP-MS-81-18,
E. I. du Pont de Nemours & Co., Savannah River Laboratory
,
Aiken, SC
,
1981
.
11.
Flaherty
,
J. E.
,
Fujita
,
A.
,
Deltete
,
C. P.
, and
Quinn
,
G. J.
,
A Calculational Technique to Predict Gas Generation in Sealed Radioactive Waste Containers
, GEND 041,
EG&G Idaho, Inc.
,
Idaho Falls, ID
,
1986
.
12.
Friedman
,
H. A.
,
Dole
,
L. R.
,
Gilliam
,
T. M.
, and
Rogers
,
G. C.
,
Radiolytic Gas Generation Rates from Hanford RHO-CAW Sludge and Double-Shell Slurry Immobilization in Grout
, ORNL/TM-9412,
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
1985
.
13.
Gaumann
,
T.
, and
Hoigné
,
J.
, Eds.,
Aspects of Hydrocarbon Radiolysis
,
Academic Press
,
London, England
,
1968
.
14.
Henrie
,
J. O.
and
Postma
,
A. K.
,
Analysis of Three Mile Island Unit 2 Hydrogen Burn
, RHO-RE-SA-8,
Rockwell Hanford Operations
,
Richland, WA
,
1983
;
also GEND-023, Vol. IV,
EG&G Idaho, Inc.
,
Idaho Falls, ID
.
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