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93.Hobson D. Texture Changes produced during Zircaloy-4 Tubing Fabrica­ tion.— ASTM STP-458, 1969, p. 37.

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95. Howe L., Tomas W. Effect of Neutron irradiation

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96. Howl D. A. The Prediction of Instantaneous Collapse Pressure for Fuel Cladding for Pressurized Water Reactor.— «J. Brit. Nucl. Energy Soc» 1965, v. 4, No. 4, p. 337.

97.Ibrahim E. F. An Equation for Creep of Cold Worked Zircaloy Pressure Tube Materials — AECL-2528, 1965.

98.Irwin G. R. Fracture Dynamics. In: «Fracture Metals», ASM, Clevelend, 1948, p. 147—166.

99.Irwin G. R. Relation of Crack Toughness Measurements to Practical Ap­ plications.— «Weld. J.», 1962, v. 41, No. 11, p. 519.

100. Irvin J. Effects of

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104.Jung-Konig W. е. a. Untersuchung des Einflusses der Neutronenbestrah-

 

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Program.— USAEC Re­

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1964.

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1967.

 

 

 

 

 

108.Klepfer H., Douglass D. Factor limiting the use of Zirconium alloys in superheated steam.— ASTM STP 376, 1968, p. 118.

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Structure of cold-rolled

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X-ray diffraction and

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112. Langford W. J. Metallurgical properties of Cold-Worked Zircaloy-2 pressu­

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NPD

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113. Lastman B. e. a. Zircaloy Cladding Performs

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N. Y.,

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1966.

 

 

 

 

 

Zircaloy-2.— Procee­

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122.

Marshall R., Louthan M. Tensile properties of Zircaloy with oriented hyd­

123.

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124.Marhall R. Control Hydride orientation in Zircaloy by fabrication practi­ ce.— «J. Nucl. Materials», 1967, v. 24, No. 1, p. 49.

125.May M., Irmcher J. Einflub von kleinen Niobgehalten auf die Rekristalli-

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Strain

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127. Nichols R. W., Watkins

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128.Nichols R. e. a. SGITWR and other heavy water reactors.— Proceeding Conference on Steam Generating and other Heavy Water Reactors, Lond.,

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129.Nihols F. A. Theory of the Creep of Zircaloy during neutron Irradiation.— «J. Nucl. Materials», 1969, v. 30, p. 249.

130.Nichols F. A. On the Mechanisms of Irradiation Creep in Zirconium-Base Alloys.— «J. Nucl. Materials», 1970, v. 37, p. 59.

131.Novak S. R., Rofle S. T. Comparision of Fracture Mechanics and Nominal

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132.Nuclear Power, World Reactor Chart, 1962, v. 7, No. 69.

133.New Heat Treatment Cuts Zircaloy-2 Corrosion, Hydrogen Embrittle­ ment.— «Nucleonics», 1963, No. 11, p. 70.

134.O’Donnel W. J., Langer B. F. Fatigue Design Basis for Zircaloy Compo­

135.

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Page R. Engineering and performance

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137.

Pankaskie P. J. Creep Properties of Zircaloy-2 for Design Application.—

138.

HW-75267, UC-25, 1962.

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of Crack Propagation

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140. Paris P. C., Erdogan F. A. Critical Analysis

 

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141.Parry G., Evans j . Occurarice of ductile hydride in Zircaloy-2. «Nucleo­ nics», 1964, v. 22, No. 11, p. 65.

142.

Parry

G. Stress

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Zr — 2,5% Nb

 

pressure tube.— AECL-2624,

1966.

Irradiation on the Tensile Properties

143. Parry

G. The effect of Fast

neutron

 

of

Specimens

from

Cold-Worked

Zd.— 2.5%Nb

pressure

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144.

AECL-2625, 1966.

 

 

Design.— «Weld. J.», 1971,

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Pellini

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Zircaloy-2 stainless steel

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146.

Perona

G. e. a.

Study

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147.

«J. Nucl. Materials», 1966, v. 18, No. 3, p. 278.

 

 

 

Picklesimer F. A. Preliminary Examination of the Formation and Utiliza­

148.

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149.

Power

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150.Progress in Measuring Fracture Toughness and Using Fracture Mechanics (Fith Report of a Special ASTM Committee). — «Materials Research and Standarts», 1964, v. 4, p. 107.

151. Robertson T. S. Propagation of Brittle Fracture in Steel.— «J. Iron and Steel Inst.», 1953, v. 175, p. 361.

152.Ross-Ross P. A. Fuel Channel development for Canada’s Power Reac­ tors.— AECL-3126, 1968.

153.Ross-Ross P. A., Hunt С. E. L. The in-reactor Creep of Cold-Worked Zir-

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154.Rowe R. G., Hoagland R. G. The Effects of Cold Work, Thermal Trearment and Neutron Irradiation on the Fracture Toughness of Zircaloy-2.— Radiation on Structural Metals, ASTM STP 457, 1969, p. 3.

155.Rubel H. e. a. Wasserstoffaufnahme und Wasserstoffversprodung Von Zir­

156.

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1964,

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Ruckdeschel

W., Wiencierz

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Entwicklung

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nium— Niob — Legrerungen

mit

hoher Fostigkeittur

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1968,

157.

S. 117.

R.

Coefficients

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158.Schreiber R. E., Allio R. J. Multiaxial Strain Fatigue in Zircaloy-4.— «Electrochem. Technol.», 1966, v. 4, No. 5—6, p. 347.

159.Seddon B. J. Zirconium Data Mannal Properties of Interest in Reactor Design — Complied.— TRG-Report, 1962, p. 108.

160.Sinha T., Arunachalam V. Influence of texture on mechnical properties of

Zircaloy-2 containing stress-oriented hydrides.— Govt India Atomic Energgy Commis. BARC-367, 1968.

161.Skelly H„ Dixon C. F. Zirconium-refractory alloys.«J. Less Common Metals.», 1971, v. 23, No. 8, p. 415.

162.Slattery G. The effects of hydride on the thermal expansivity of Zirconium alloys.— «Less Common eMtals», 1966, No. 2, p. 89.

163.Slattery G. F. The Prediction of Collapse Pressure for Anisotropic Zirca­

 

loy-2 Tubing Using Tensile Stress-Strain

Date. — TRG-Report

1476 (s),

164.

1967.

 

 

 

 

 

 

 

Slattery G. The Terminal Solubility of Hydrogen in Zirconium Alloys Bet­

165.

ween 30

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Slattery G. The Mechanical Properties of

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Soo P., Higgins G. The deformation of Zirconium-oxygen single crys­

167.

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1968, v. 16, p. 177.

Fuel

Sheat­

Steward

K. The properties

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168.Steward K-, Cheadle B. The effect of preferred orientation on mechanical properties and deformation behaviour of Zircaloy-2 fuel sheathing.— AECL-2627, 1966.

166