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Companion Guide to the ASME Boiler and Pressure Vessel Codes, Volume 1, Fifth Edition

Editor
K.R. Rao
K.R. Rao
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ISBN:
9780791861301
No. of Pages:
872
Publisher:
ASME Press
Publication date:
2018
1.
ASME Boiler and Pressure Vessel Code Section III, Division 1, Nuclear Components
;
The American Society of Mechanical Engineers
.
2.
Criteria of the ASME Boiler and Pressure Vessel Code Sections III and VIII, Division 2, Design by Analysis
;
1969
,
The American Society of Mechanical Engineers
.
3.
ANSI B31.7, Nuclear Power Piping
;
The American National Standards Institute
.
4.
ANSI B16.28, Wrought Steel Short Radius Elbows
;
The American National Standards Institute
.
5.
Tagart
,
S. W.
, “
Plastic Fatigue Analysis of Pressure Components
,”
Pressure Vessel and Piping, Design and Analysis
,
PVP-Vol. 1
,
1972
.
6.
ANSI B16.9, Factory Made Wrought Steel Butt Welded Fittings
.
7.
Waters
,
E. O.
,
Wesstrom
,
D. B.
,
Rossem
,
D. B.
, and
Williams
,
F. S. G.
, “
Formulas for Stresses in Bolted Flanged Connections
,” Reprinted from
1937 ASME Transactions
.
8.
ANSI B31.1, Power Piping
;
The American National Standards Institute
.
9.
Langer
,
B. F.
, “
Design of Pressure Vessels for Low-Cycle Fatigue
,”
Journal of Basic Engineering
,
1962
.
10.
Markl
,
A. R. C.
, “
Fatigue Tests of Piping Components
,”
Transactions ASME
, Vol.
74
, No.
3
, pp.
287
299
,
1952
.
11.
Markl
,
A. R. C.
, “
Piping Flexibility Analysis
,” Reprinted from
ASME Transactions
, pp.
419
441
,
1955
.
12.
ASME Boiler and Pressure Vessel Code Section III, Division 1, Paragraph NB-3200, Nuclear Components
;
The American Society of Mechanical Engineers
,
1978
.
13.
ASME Boiler and Pressure Vessel Code Section III, Division 1, Paragraphs NB-3600, NC-3600, and ND-3600, Nuclear Components
;
The American Society of Mechanical Engineers
.
14.
Cooper
,
W. E.
, “
The Initial Scope and Intent of the Section III Fatigue Design Procedures
,”
Paper presented at PVRC Workshop on Cyclic Life and Environmental Effects in Nuclear Applications
,
January 1992
.
15.
Tagart
,
S. W.
, “
Basis for Paragraph NB-3228.3 of ASME Section III, Simplified Elastic—Plastic Analysis
.”
16.
Langer
,
B. F.
, “
Fatigue Evaluation for Primary-Plus-Secondary Stresses which Exceed 3Sm
,“
June
1969
.
17.
Tagart
,
S. W.
, “
Plastic Fatigue Analysis of Pressure Components
,”
Pressure Vessels and Piping, Design and Analysis
,
PVP-Vol. 1
,
The American Society of Mechanical Engineers, ASME
1972
.
18.
WRC 285
,
Avent
,
R. R.
,
Sadd
,
M. H.
, and
Rodabaugh
,
E. C.
(
1983
). “
Finite Element Analysis of Eccentric Reducers and Comparisons with Concentric Reducers
,”
Welding Research Council, Bulletin 285
,
New York
.
19.
WRC 285
,
Rodabaugh
E. C.
, and
Moore
,
S. E.
(
1983
). “
Stress Indices and Flexibility Factors for Concentric Reducers
,”
Welding Research Council, Bulletin 285
,
New York
.
20.
.
WRC 179
,
Dodge
,
W. G.
, and
Moore
,
S. E.
(
1979
). “
Stress Indices and Flexibility Factors for Moment Loadings on Elbows and Curved Pipe
,”
Welding Research Council, Bulletin 179
,
New York
.
21.
ANSI/ASME B31.1, Power Piping
;
The American Society of Mechanical Engineers
.
22.
ANSI B16.5, Steel Pipe Flanges and Flanged Fittings
;
The American National Standards Institute
.
23.
ANSI B16.11, Forged Steel Fittings, Socket-Welding and Threaded
;
The American National Standards Institute
.
24.
King
,
R. C.
, and
Crocker
,
S.
,
Piping Handbook
,
5
th ed.,
McGraw-Hill
,
1967
.
25.
Rodabaugh
,
E. C.
, “
Comparisons of ASME Code Fatigue Evaluation Methods for Nuclear Class 1 Piping with Class 2 or 3 Piping
,”
NUREG/CR-3243, Oak Ridge National Laboratory
,
Oak Ridge, TN
.
26.
Markl
,
A. R. C.
, “
Fatigue Tests of Welding Elbows and Comparable Double-Miter Bends
,”
Transactions ASME
, Vol.
69
, No.
8
, pp.
869
879
,
Nov.
1947
.
27.
Markl
,
A. R. C.
, and
George
,
H. H.
, “
Fatigue Tests on Flanged Assemblies
,” Reprinted from
ASME Transactions
, pp.
91
101
,
1950
.
28.
WRC 361
,
Grandemange
,
J. M.
,
Heliot
,
J.
,
Vagner
,
J.
,
Morel
,
A.
, and
Faidy
,
C
. (
1991
) “
Improvements on Fatigue Analysis Methods for the Design of Nuclear Components Subjected to the French RCC-M Code
,”
Welding Research Council, Bulletin 361
,
New York
.
29.
WRC 361
,
Heng
,
C.
, and
Grandemange
,
J. M.
(
1991
). “
Framatome View of the Comparison between Class 1 and Class 2 RCC-M Piping Design Rules
,”
Welding Research Council Bulletin 361
,
New York
.
30.
ASME Boiler and Pressure Vessel Code Section II
;
The American Society of Mechanical Engineers
.
31.
ASME Boiler and Pressure Vessel Code, Section III Division 1 Appendices, Appendix W, Environmental Effects on Components
.
32.
Operation and Maintenance of Nuclear Power Plants, ASME OM Code
.
33.
Design, Fabrication, and Materials Code Case Acceptability, ASME III, USNRC Regulatory Guide 1.84, Revision 36
,
October
2014
.
34.
Guidelines for Evaluating Fatigue Analyses incorporating the Life Reduction of Metal Components Due to the Effect of the Light-Water Reactor Environment for New Reactors, USNRC Regulatory Guide 1.207
,
March
2007
.
35.
Standard Review Plan for Review of License Renewal Application for Nuclear Power Plants, (NUREG-1800) Rev 2
,
December
2010
.
36.
.
Preliminary Basis for Potential Reduction in Pipe Fitting Stress Indices, EPRI Materials Reliability Program, MRP-261
,
Hollinger and Rodabaugh
.
37.
ASME Code Class 1, 2, and 3 Piping System, Piping Components, and their Associated Supports, NUREG-0800, SRP 3.12
,
March
2007
.
38.
EPRI
,
Materials Reliability Program
,
Assessment of RHR Mixing Tee Thermal Fatigue in PWR Plants (MRP-192, Revision 1)
,
November
2008
.
39.
EPRI
,
Mitigation of Thermal Fatigue in Unisolable Piping Connected to PWR Reactor Coolant Systems (MRP-29)
,
2000
.
40.
EPRI
,
Vibration Fatigue Testing of Socket Welds, PWRMRP-07, TR-113890
,
December
1999
.
41.
Vibration Analysis of BWR/5 Recirculation System Piping
,
Proceedings of ICONE-8, ICONE-8682
,
April 2000
,
Martin
Torres
,
Jack
Cole
, and
Abbas
Mostala
.
42.
Vibration Testing of BWR/5 Recirculation Piping System, Vibration
,
Torres
,
Cole
, and
Mostala
,
2000
PVP Vol. 409
.
43.
ASME Boiler and Pressure Vessel Code 2015 Edition Section III, Rules for Construction of Nuclear Facility Components
.
44.
Chopra
,
O. K.
and
Shack
,
W. J.
, “
Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials
,”
NUREG/CR-6909, ANL-06/08
,
U.S. Nuclear Regulatory Commission
,
Washington, DC
,
February
2007
.
45.
Guidelines for Addressing Environmental Effects in Fatigue Usage Calculations
.
EPRI
,
Palo Alto, CA
:
2012
.
1025823
.
46.
ASME Code Case N-755-2, Use of Polyethylene (PE) Class 3 Plastic Pipe Section III, Division 1
,
August
13
,
2013
.
47.
Plastic Pipe Institute Handbook of PE Pipe, Second Edition
.
48.
ASME Code Case N-806-1, Analytical Evaluation of Metal Loss in Class 2 and 3 Metallic Piping Buried in a Back-Filled Trench, Section XI, Division 1
.
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