PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JULY 1958
Data are given on the thermal ccnductivity of Ti--6 wt. % Al--4 wt.% V. The creep strength of 15% cold-worked Zircaloy-2 is being determined for reactor components in the 290 to 400 deg C range. Nine serles of high-strength corrosion- resistant Zr alloys were prepared and corrosion tested. Results are included. The fabrication of Al-U alloys for uses in various reactors is presented. The development of a natural-U fuel alloy with improved corrosion resistance is presented. Results of corrosion tests on the natural--U alloy are presented. A study is presented to investigate the possibilities of applying a thin protectlve coating of Mo on the interior surfaces of the reactor system by electroless and vapor-plating techniques. An irradiation-damage program to detcrmine the extent of damage to type 347 stainless steel in iast-neutron fluxes in the core of the ETR is presented. The properties of the high-niobium portion of the Nb-U constitution diagram are presented. The development of Th-U alloys with increased irradiation stability and corrosion resistance is presented. Dispersion-type fuel specimens containing 24 wt.% fully enriched UC and UN dispersed in a l8 wt.% Cr14 wt.% Ni-2.5 wt.% Mo--balance Fe matrix and clad with type 318 stainless steel were fabricated for irradiation testing. Gas-pressure bonding is being investigated as a technique for the cladding and bonding of Nb and Mo fuel elements. Corrosion testing of Ti in Darex Process dissolver solution is presented. Studies were continued on ways of preventing stress- corrosion cracking of Carpenter 20 Cb in the Sulfex-Thorex system. A run is under way in a new molten-salt composition (62 M% NaF-38 M% ZrF/sub 4/). Specimens of INOR-1 and INOR-8, Hastelloy B, and type S-816 are being tested. A program is presented for the preparation of as-cast irradiation-test specimens of UC and the determination of some physical properties of UC. The postirradiation examination of twelve Th-11 wt.% U speci mens irradiated in two capsule trains has been completed. Creep data are presented on thermally degassed fine-grained sintered Ta sheet tested at 1200 F in a He atmosphere. A program to investigate the effects of reactor radiations on clad graphite specimens is in progress. The current work on the Nuclear Merchant Ship Reactor Program is primarily concerned with the development of fabrication techniques for UOsub 2/- containing fuel pins for a dynamic loop test at the MTR. (For preceding period see BMI-1273.) (W.L.H.)
- Research Organization:
- Battelle Memorial Inst., Columbus, OH (United States)
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-13-000186
- OSTI ID:
- 4300575
- Report Number(s):
- BMI-1280
- Resource Relation:
- Other Information: Decl. Oct. 7, 1958. Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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