Author: S. Venugopal
Publisher:
ISBN:
Category : Accelerated irradiation test
Languages : en
Pages : 16
Book Description
Fast Breeder Test Reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, India is a sodium cooled fast reactor with a maximum neutron flux of about 3 x 1015 n/cm2/s. The neutron spectrum in the FBTR is hard and the damage rate attained in structural specimens is high. Compact pressurized capsules of zirconium alloys have been developed and subjected to irradiation in the FBTR to a fluence level of 1.1 x 1021 n/cm2 (E >1 MeV) at temperatures of 306 to 319°C to determine the irradiation creep rate of indigenously developed zirconium alloys (Zircaloy-2 and Zr-2.5%Nb alloy). To assess the changes in mechanical properties of FBTR grid plate material (modified type 316 stainless steel) due to prolonged low dose exposure, an accelerated irradiation test with dose levels up to 2.6 dpa (at 350°C) has also been carried out using miniature tensile test and disk specimens. Postirradiation examination (PIE) measurements carried out in the hot cells determined the creep rate of zirconium alloys, and indicated that the grid plate material has hardened but has still enough residual ductility. This paper presents salient features of the design and implementation of these irradiation experiments in FBTR and the results obtained during PIE.
Irradiation Testing of Zirconium Alloys and Stainless Steel in Fast Breeder Test Reactor, India
Author: S. Venugopal
Publisher:
ISBN:
Category : Accelerated irradiation test
Languages : en
Pages : 16
Book Description
Fast Breeder Test Reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, India is a sodium cooled fast reactor with a maximum neutron flux of about 3 x 1015 n/cm2/s. The neutron spectrum in the FBTR is hard and the damage rate attained in structural specimens is high. Compact pressurized capsules of zirconium alloys have been developed and subjected to irradiation in the FBTR to a fluence level of 1.1 x 1021 n/cm2 (E >1 MeV) at temperatures of 306 to 319°C to determine the irradiation creep rate of indigenously developed zirconium alloys (Zircaloy-2 and Zr-2.5%Nb alloy). To assess the changes in mechanical properties of FBTR grid plate material (modified type 316 stainless steel) due to prolonged low dose exposure, an accelerated irradiation test with dose levels up to 2.6 dpa (at 350°C) has also been carried out using miniature tensile test and disk specimens. Postirradiation examination (PIE) measurements carried out in the hot cells determined the creep rate of zirconium alloys, and indicated that the grid plate material has hardened but has still enough residual ductility. This paper presents salient features of the design and implementation of these irradiation experiments in FBTR and the results obtained during PIE.
Publisher:
ISBN:
Category : Accelerated irradiation test
Languages : en
Pages : 16
Book Description
Fast Breeder Test Reactor (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, India is a sodium cooled fast reactor with a maximum neutron flux of about 3 x 1015 n/cm2/s. The neutron spectrum in the FBTR is hard and the damage rate attained in structural specimens is high. Compact pressurized capsules of zirconium alloys have been developed and subjected to irradiation in the FBTR to a fluence level of 1.1 x 1021 n/cm2 (E >1 MeV) at temperatures of 306 to 319°C to determine the irradiation creep rate of indigenously developed zirconium alloys (Zircaloy-2 and Zr-2.5%Nb alloy). To assess the changes in mechanical properties of FBTR grid plate material (modified type 316 stainless steel) due to prolonged low dose exposure, an accelerated irradiation test with dose levels up to 2.6 dpa (at 350°C) has also been carried out using miniature tensile test and disk specimens. Postirradiation examination (PIE) measurements carried out in the hot cells determined the creep rate of zirconium alloys, and indicated that the grid plate material has hardened but has still enough residual ductility. This paper presents salient features of the design and implementation of these irradiation experiments in FBTR and the results obtained during PIE.
Irradiation Effects in Structural Alloys for Thermal and Fast Reactors
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 437
Book Description
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 437
Book Description
Non-Linear Irradiation Growth of Cold-Worked Zircaloy-2
Author: RA. Holt
Publisher:
ISBN:
Category : Congress
Languages : en
Pages : 15
Book Description
Accelerating irradiation growth has been reported for several zirconium alloys with a range of metallurgical states during high-temperature tests in fast-breeder reactors (673 to 723 K) for annealed Zircaloys in thermal test reactors at power reactor temperatures (523 to 623 K) and in power reactor core components fabricated from annealed or recrystallized Zircaloy. In the latter case, there was a transition from low to high irradiation growth rates at moderate fluences (about 3 x 1025 n/m2, E > 1 MeV, at 580 K) related to the nucleation and growth of basal plane c-component loops.
Publisher:
ISBN:
Category : Congress
Languages : en
Pages : 15
Book Description
Accelerating irradiation growth has been reported for several zirconium alloys with a range of metallurgical states during high-temperature tests in fast-breeder reactors (673 to 723 K) for annealed Zircaloys in thermal test reactors at power reactor temperatures (523 to 623 K) and in power reactor core components fabricated from annealed or recrystallized Zircaloy. In the latter case, there was a transition from low to high irradiation growth rates at moderate fluences (about 3 x 1025 n/m2, E > 1 MeV, at 580 K) related to the nucleation and growth of basal plane c-component loops.
Zirconium in the Nuclear Industry
Author: ASTM Committee B-10 on Reactive and Refractory Metals and Alloys
Publisher: ASTM International
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 694
Book Description
Publisher: ASTM International
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 694
Book Description
Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design
Author: C. L. Whitmarsh
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 74
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 74
Book Description
Zirconium in the Nuclear Industry
Author: D. Franklin
Publisher: ASTM International
ISBN: 9780803107540
Category : Business & Economics
Languages : en
Pages : 516
Book Description
Publisher: ASTM International
ISBN: 9780803107540
Category : Business & Economics
Languages : en
Pages : 516
Book Description
The Use of Small-scale Specimens for Testing Irradiated Material
Author: W. R. Corwin
Publisher: ASTM International
ISBN: 0803104405
Category : Alloys
Languages : en
Pages : 387
Book Description
Publisher: ASTM International
ISBN: 0803104405
Category : Alloys
Languages : en
Pages : 387
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 680
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 680
Book Description
Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels
Author: Lendell E. Steele
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 252
Book Description
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 252
Book Description
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1038
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1038
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.