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|  Supplemental Material
4.2.4
NUREG-0800, USNRC "Standard Review Plan," June
A.
1987.
"Fuel System Design."
1.
SRP 4.2,
NUREG-0630, "Cladding Swelling and Rupture Models
B.
for LOCA Analysis," USNRC, April 1980.
NUREG-0401, "Fuel Failure Detection in Operating
C.
Reactors," USNRC, March 1978.
D.
"The Analysis of Fuel Densification,"
NUREG-0085,
USNRC, July 1976.
NUREG/CR-1883 , "Multirod Burst Test Program Prog-
E.
ress Report for January-June 1980," R.H. Chapman, Oak Ridge
National Laboratory, March 1981.
NUREG/CR-1380, "Assessment of Current Onsite
F.
Inspection Techniques for LWR Fuel Systems," W.J. Bailey, et al.,
Battelle Pacific Northwest Laboratory, Vol. 1 July 1980, Vol. 2,
January 1981.
G.
WASH-1236, "Technical Report on Densification of
Light Water Reactor Fuels," USAEC, November 14, 1972.
H.
"Burst Criterion of Zircaloy Fuel Claddings in a
LOCA," F. Erbacher, H.J. Neitzel, H. Rosinger, H. Schmidt, and K.
Wiehr, ASTM Fifth International Conference on Zirconium in the
Nuclear Industry, August 4-7, 1980, Boston, Massachusetts.
BNWL-1898, "GAPCON-THERMAL-2 :
I.
A Computer Program
for Calculating the Thermal Behavior of an Oxide Fuel Rod," C.E.
Beyer, C.R. Harm, D.D. Lanning, F.E. Panisko and L.J. Parchen,
Battelle Pacific Northwest Laboratory, November 1975.
BNWL-1897, "User's Guide for GAPCON-THERMAL-2: A
J.
Computer Program for Calculating the Thermal Behavior of an Oxide
Fuel Rod," C.E. Beyer, C.R. Harm, D.D. Lanning, F.E. Panisko and
L.J. Parchen, Battelle Pacific Northwest Laboratory, November
1975.
K.
ANL-6548, "Studies of Metal-Water Reactions at High
Temperatures, III.
Experimental and Theoretical Studies of the
Zirconium-Water Reaction," L. Baker and L.C. Just, Argonne
National Laboratory, May 1962.
4-3
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