Irradiation effects of boron carbide used as control rod elements in fast breeder reactors

1978 ◽  
Vol 74 (1) ◽  
pp. 114-122 ◽  
Author(s):  
Tadashi Inoue ◽  
Takeo Onchi ◽  
Hiroaki Kôyama ◽  
Hiroshige Suzuki
Keyword(s):  
Boron Carbide ◽  
Irradiation Effects ◽  
Control Rod ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

Absorber materials for control rod systems of fast breeder reactors

1984 ◽  
Vol 124 ◽  
pp. 185-194 ◽  
Author(s):  
Ph. Dünner ◽  
H.-J. Heuvel ◽  
M. Hörle
Keyword(s):  
Control Rod ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

2000 ◽  
Vol 123 (1) ◽  
pp. 49-57 ◽  
Author(s):  
Tai Asayama ◽  
Yasuhiro Abe ◽  
Noriko Miyaji ◽  
Mamoru Koi ◽  
Tomohiro Furukawa ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Environmental Effects ◽  
Structural Design ◽  
Neutron Fluence ◽  
Evaluation Procedure ◽  
Fast Breeder Reactor ◽  
Irradiation Effects ◽  
Creep Life ◽  
Fast Breeder Reactors ◽  
Breeder Reactors

In the structural design of fast breeder reactors, irradiation effects and sodium environmental effects on structural materials have to be taken into account. In this paper, firstly, an evaluation procedure for irradiation effects on the mechanical properties of 316FR (FBR Grade 316 stainless steel), which is a newly developed stainless steel for the Japanese demonstration fast breeder reactor, is proposed. The procedure gives a limit of accumulated fast neutron fluence E>0.1 MeV as a function of temperature, so that the minimum tensile fracture elongation of 10 percent, which is the threshold for material to stay ductile, is maintained. Furthermore, the procedure determined a creep life reduction factor and a creep rate increase factor as a function of accumulated thermal neutron fluence E<0.4 eV, within the limitation of the accumulated fast neutron fluence, to account for the creep life reduction and the increase of creep rate due to irradiation. Secondly, an evaluation procedure for sodium environmental effects on the integrity of 316FR and modified 9Cr-1Mo steel was proposed. It gave a corrosion allowance as a function of temperature, oxygen content, and service time, based on corrosion tests. It determined that no correction factors that correspond to sodium environment on design allowable stresses, etc., are needed, because no adverse effects of sodium on the mechanical properties of 316FR and modified 9Cr-1Mo steel were to be expected in the service conditions of FBRs. Both the procedures have been incorporated into the Japanese Elevated Temperature Structural Design Guide for Demonstration Fast Breeder Reactor.

Utilization Research and Development of Hydride Materials in Fast Reactors

2014 ◽  
Vol 94 ◽  
pp. 23-31 ◽  
Author(s):  
Kenji Konashi ◽  
Kunihiro Itoh ◽  
Tsugio Yokoyama ◽  
Michio Yamawaki
Keyword(s):  
Cross Sections ◽  
Fast Neutrons ◽  
High Hydrogen ◽  
Neutron Absorber ◽  
Control Rod ◽  
Irradiation Test ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Hafnium Hydride ◽  
Control Rods

Metal hydrides have high hydrogen atom density, which is equivalent to that of liquid water. An application of the hafnium hydride has been investigated as a neutron absorber in the Fast Breeder Reactors (FBRs). Fast neutrons are efficiently moderated by hydrogen in Hf hydrides and are absorbed by Hf. Since three isotopes of Hf have large cross sections, increase in the life of control rod is considered by Hf hydride. Results of design study of the core with Hf hydride control rods shows that the long lived hafnium hydride control rod is feasible in the large sodium-cooled FBR. Results of irradiation test conducted in BOR-60 has demonstrated the integrity of the capsules during irradiation. Na bonded capsule has an advantage in confinement effect of hydrogen compared with He bonded one. An application of hydride technique to transmutation target of MA was also discussed. MA hydride target is able to enhance the transmutation rate in FBR.

Pressureless Sintering of B4C Neutron Absorbing Material with Nano-Sized Rare-Earth Compounds Addition

2012 ◽  
Vol 602-604 ◽  
pp. 503-507
Author(s):  
Ru Bin Wei ◽  
Yu Jun Zhang ◽  
Hong Yu Gong ◽  
Xiao Jun Liu ◽  
Ya Zhen Jiang ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Rare Earth ◽  
Boron Carbide ◽  
Pressureless Sintering ◽  
Rare Earth Compounds ◽  
Neutron Absorber ◽  
Absorbing Material ◽  
Fast Breeder Reactors ◽  
Dysprosium Titanate ◽  
Breeder Reactors

The processing of boron carbide by pressureless sintering with nano-sized rare-earth compounds additives to obtain dense pellets for use as neutron absorber in fast breeder reactors is investigated. The effect of dysprosium aluminum garnet (DAG) and dysprosium titanate nanopowders on density and mechanical properties was studied. The addition of DAG and dysprosium titanate nanopowders was found to be beneficial in the densification of B4C powders. B4C with 5 wt. % of DAG or dysprosium titanate nanopowders, exhibiting bulk density of 2.14g/cm3 and 2.35 g/cm3, could be prepared by pressureless heating at 2120°C and 2160°C.

Radiation Damage Studies with the HVEM

1972 ◽  
Vol 30 ◽  
pp. 680-681
Author(s):  
J. J. Laidler ◽  
B. Mastel
Keyword(s):  
Radiation Damage ◽  
Stainless Steels ◽  
Volume Expansion ◽  
Austenitic Stainless Steels ◽  
Test Facility ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Under Construction ◽  
Development Laboratory ◽  
Insight Into

One of the major materials problems encountered in the development of fast breeder reactors for commercial power generation is the phenomenon of swelling in core structural components and fuel cladding. This volume expansion, which is due to the retention of lattice vacancies by agglomeration into large polyhedral clusters (voids), may amount to ten percent or greater at goal fluences in some austenitic stainless steels. From a design standpoint, this is an undesirable situation, and it is necessary to obtain experimental confirmation that such excessive volume expansion will not occur in materials selected for core applications in the Fast Flux Test Facility, the prototypic LMFBR now under construction at the Hanford Engineering Development Laboratory (HEDL). The HEDL JEM-1000 1 MeV electron microscope is being used to provide an insight into trends of radiation damage accumulation in stainless steels, since it is possible to produce atom displacements at an accelerated rate with 1 MeV electrons, while the specimen is under continuous observation.

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