1
U.S. Government:Tausend Und Eine Nacht Arabische Erzahlungen (16-18) - Paperback
ISBN: 1234449269
[EAN: 9781234449261], Neubuch, [PU: RareBooksClub], U.S. GOVERNMENT,SUBJECTS, This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engine… More...
[EAN: 9781234449261], Neubuch, [PU: RareBooksClub], U.S. GOVERNMENT,SUBJECTS, This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U. S. Nuclear Regulatory Commission, 1995 OCLC Number: (OCoLC)238374168 Subject: Nuclear reactors -- Materials -- Mechanical properties. Excerpt: . . . 1 Introduction Cast duplex stainless steels ( SSs ) are used extensively in the nuclear industry for valve bodies, pump casings, and primary coolant piping. The ferrite phase in the duplex structure of austenitic - ferritic SSs increases the tensile strength and improves the soundness of casting, weldability, and resistance to stress corrosion cracking of these steels. However, these steels are susceptible to thermal embrittlement after extended service at reactor operating tempera-tures, i. e. , typically 282 C ( 540 F ) for boiling water reactors, 288 - 327 C ( 550 - 621 F ) for pressurized water reactor ( PWR ) primary coolant piping, and 343 C ( 650 F ) for PWR pressuriz-ers. Thermal aging of cast SSs at these temperatures causes an increase in hardness and tensile strength; decrease in ductility, impact strength, and fracture toughness of the material; and a shift of the Charpy transition curve to higher temperatures. Therefore, to evaluate the performance of cast SS components during prolonged exposure to service temperatures, we must assess the mechanical - property degradation that is due to thermal embrittlement, be-cause rupture of the primary pressure boundary could lead to a loss - of - coolant accident and possible exposure of the public to radiation. 1 - 8 9 - 16 Investigations at Argonne National Laboratory ( ANL ) and elsewhere have shown that thermal embrittlement of cast SSs ( i. e. , ASTM Specification A - 351 grades CF - 3, CF - 3A, CF - 8, CF - 8A, and CF - 8M ) can occur during the reactor design life of 40 y. Cast SS components with even modest ferrite content, e. g. , 10 - 15 ferrite, may show significant thermal embrittlement. For example, the hot - leg elbow from the Ringhals 2. . . This item ships from La Vergne,TN.<
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U.S. Government:
Tausend Und Eine Nacht Arabische Erzahlungen (16-18)
- Paperback1995, ISBN: 9781234449261
Rarebooksclub.com. Paperback. New. This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Resea… More...
Rarebooksclub.com. Paperback. New. This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U. S. Nuclear Regulatory Commission, 1995 OCLC Number: (OCoLC)238374168 Subject: Nuclear reactors -- Materials -- Mechanical properties. Excerpt: . . . 1 Introduction Cast duplex stainless steels ( SSs ) are used extensively in the nuclear industry for valve bodies, pump casings, and primary coolant piping. The ferrite phase in the duplex structure of austenitic - ferritic SSs increases the tensile strength and improves the soundness of casting, weldability, and resistance to stress corrosion cracking of these steels. However, these steels are susceptible to thermal embrittlement after extended service at reactor operating tempera-tures, i. e. , typically 282 C ( 540 F ) for boiling water reactors, 288 - 327 C ( 550 - 621 F ) for pressurized water reactor ( PWR ) primary coolant piping, and 343 C ( 650 F ) for PWR pressuriz-ers. Thermal aging of cast SSs at these temperatures causes an increase in hardness and tensile strength; decrease in ductility, impact strength, and fracture toughness of the material; and a shift of the Charpy transition curve to higher temperatures. Therefore, to evaluate the performance of cast SS components during prolonged exposure to service temperatures, we must assess the mechanical - property degradation that is due to thermal embrittlement, be-cause rupture of the primary pressure boundary could lead to a loss - of - coolant accident and possible exposure of the public to radiation. 1 - 8 9 - 16 Investigations at Argonne National Laboratory ( ANL ) and elsewhere have shown that thermal embrittlement of cast SSs ( i. e. , ASTM Specification A - 351 grades CF - 3, CF - 3A, CF - 8, CF - 8A, and CF - 8M ) can occur during the reactor design life of 40 y. Cast SS components with even modest ferrite content, e. g. , 10 - 15 ferrite, may show significant thermal embrittlement. For example, the hot - leg elbow from the Ringhals 2. . . This item ships from La Vergne,TN., Rarebooksclub.com<
- Shipping costs: EUR 9.73 BuySomeBooks
3
U.S. Government:Tausend Und Eine Nacht Arabische Erzahlungen (16-18)
- Paperback 1995
ISBN: 9781234449261
RareBooksClub. Paperback. New. This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research,… More...
RareBooksClub. Paperback. New. This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U. S. Nuclear Regulatory Commission, 1995 OCLC Number: (OCoLC)238374168 Subject: Nuclear reactors -- Materials -- Mechanical properties. Excerpt: . . . 1 Introduction Cast duplex stainless steels ( SSs ) are used extensively in the nuclear industry for valve bodies, pump casings, and primary coolant piping. The ferrite phase in the duplex structure of austenitic - ferritic SSs increases the tensile strength and improves the soundness of casting, weldability, and resistance to stress corrosion cracking of these steels. However, these steels are susceptible to thermal embrittlement after extended service at reactor operating tempera-tures, i. e. , typically 282 C ( 540 F ) for boiling water reactors, 288 - 327 C ( 550 - 621 F ) for pressurized water reactor ( PWR ) primary coolant piping, and 343 C ( 650 F ) for PWR pressuriz-ers. Thermal aging of cast SSs at these temperatures causes an increase in hardness and tensile strength; decrease in ductility, impact strength, and fracture toughness of the material; and a shift of the Charpy transition curve to higher temperatures. Therefore, to evaluate the performance of cast SS components during prolonged exposure to service temperatures, we must assess the mechanical - property degradation that is due to thermal embrittlement, be-cause rupture of the primary pressure boundary could lead to a loss - of - coolant accident and possible exposure of the public to radiation. 1 - 8 9 - 16 Investigations at Argonne National Laboratory ( ANL ) and elsewhere have shown that thermal embrittlement of cast SSs ( i. e. , ASTM Specification A - 351 grades CF - 3, CF - 3A, CF - 8, CF - 8A, and CF - 8M ) can occur during the reactor design life of 40 y. Cast SS components with even modest ferrite content, e. g. , 10 - 15 ferrite, may show significant thermal embrittlement. For example, the hot - leg elbow from the Ringhals 2. . . This item ships from La Vergne,TN., RareBooksClub<
- Shipping costs: EUR 10.63 BuySomeBooks
4
Tausend Und Eine Nacht Arabische Erzahlungen (16-18)
- PaperbackISBN: 1234449269
[EAN: 9781234449261], Neubuch, [PU: RareBooksClub], SUBJECTS, This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of… More...
[EAN: 9781234449261], Neubuch, [PU: RareBooksClub], SUBJECTS, This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U. S. Nuclear Regulatory Commission, 1995 OCLC Number: (OCoLC)238374168 Subject: Nuclear reactors -- Materials -- Mechanical properties. Excerpt: . . . 1 Introduction Cast duplex stainless steels ( SSs ) are used extensively in the nuclear industry for valve bodies, pump casings, and primary coolant piping. The ferrite phase in the duplex structure of austenitic - ferritic SSs increases the tensile strength and improves the soundness of casting, weldability, and resistance to stress corrosion cracking of these steels. However, these steels are susceptible to thermal embrittlement after extended service at reactor operating tempera-tures, i. e. , typically 282 C ( 540 F ) for boiling water reactors, 288 - 327 C ( 550 - 621 F ) for pressurized water reactor ( PWR ) primary coolant piping, and 343 C ( 650 F ) for PWR pressuriz-ers. Thermal aging of cast SSs at these temperatures causes an increase in hardness and tensile strength; decrease in ductility, impact strength, and fracture toughness of the material; and a shift of the Charpy transition curve to higher temperatures. Therefore, to evaluate the performance of cast SS components during prolonged exposure to service temperatures, we must assess the mechanical - property degradation that is due to thermal embrittlement, be-cause rupture of the primary pressure boundary could lead to a loss - of - coolant accident and possible exposure of the public to radiation. 1 - 8 9 - 16 Investigations at Argonne National Laboratory ( ANL ) and elsewhere have shown that thermal embrittlement of cast SSs ( i. e. , ASTM Specification A - 351 grades CF - 3, CF - 3A, CF - 8, CF - 8A, and CF - 8M ) can occur during the reactor design life of 40 y. Cast SS components with even modest ferrite content, e. g. , 10 - 15 ferrite, may show significant thermal embrittlement. For example, the hot - leg elbow from the Ringhals 2. . . This item ships from La Vergne,TN.<
- NEW BOOK Shipping costs: EUR 11.54 BuySomeBooks, Las Vegas, NV, U.S.A. [52360437] [Rating: 5 (von 5)]
5
Tausend Und Eine Nacht Arabische Erzahlungen (16-18)
- Paperback1995, ISBN: 9781234449261
RareBooksClub. Paperback. New. This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research,… More...
RareBooksClub. Paperback. New. This item is printed on demand. Paperback. 170 pages. Original publisher: Washington, DC : Division of Engineering, Office of Nuclear Regulatory Research, U. S. Nuclear Regulatory Commission, 1995 OCLC Number: (OCoLC)238374168 Subject: Nuclear reactors -- Materials -- Mechanical properties. Excerpt: . . . 1 Introduction Cast duplex stainless steels ( SSs ) are used extensively in the nuclear industry for valve bodies, pump casings, and primary coolant piping. The ferrite phase in the duplex structure of austenitic - ferritic SSs increases the tensile strength and improves the soundness of casting, weldability, and resistance to stress corrosion cracking of these steels. However, these steels are susceptible to thermal embrittlement after extended service at reactor operating tempera-tures, i. e. , typically 282 C ( 540 F ) for boiling water reactors, 288 - 327 C ( 550 - 621 F ) for pressurized water reactor ( PWR ) primary coolant piping, and 343 C ( 650 F ) for PWR pressuriz-ers. Thermal aging of cast SSs at these temperatures causes an increase in hardness and tensile strength; decrease in ductility, impact strength, and fracture toughness of the material; and a shift of the Charpy transition curve to higher temperatures. Therefore, to evaluate the performance of cast SS components during prolonged exposure to service temperatures, we must assess the mechanical - property degradation that is due to thermal embrittlement, be-cause rupture of the primary pressure boundary could lead to a loss - of - coolant accident and possible exposure of the public to radiation. 1 - 8 9 - 16 Investigations at Argonne National Laboratory ( ANL ) and elsewhere have shown that thermal embrittlement of cast SSs ( i. e. , ASTM Specification A - 351 grades CF - 3, CF - 3A, CF - 8, CF - 8A, and CF - 8M ) can occur during the reactor design life of 40 y. Cast SS components with even modest ferrite content, e. g. , 10 - 15 ferrite, may show significant thermal embrittlement. For example, the hot - leg elbow from the Ringhals 2. . . This item ships from La Vergne,TN., RareBooksClub<
- Shipping costs: EUR 10.64 BuySomeBooks
