Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
HEAVY WATER MODERATED POWER REACTORS. Progress Report, November-December 1964
Author: HEAVY WATER MODERATED POWER REACTORS. Progress Report, November-December 1963
Author: HEAVY WATER MODERATED POWER REACTORS. Progress Report, May-June 1964
Author: HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT, SEPTEMBER-OCTOBER 1964
Author: HEAVY WATER MODERATED POWER REACTORS. Progress Report, March-April 1964
Author: Heavy water moderated power reactors : progress report : March - April 1964
Author: D. F. BabcockHeavy water moderated power reactors : progress report November 1962
Author: D. F. BabcockHeavy Water Moderated Power Reactors Progress Report for November 1959
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
At the end of November, 20% of the construction and 80% of the firm design of the Heavy Water Components Test Reactor (HWCTR) were complete. Proof testing of various seals and mechanisms for the HWCTR continued satisfatorily. Further analyses are given of the transient behavior of the HWCTR isolated coolant loops and of the experimental data on the nuclear effects of hot moderator. The results of additional fabrication and irradiation tests of uranium metal and uranium oxide are recorded. The manufacture of tubular metallurgical joints between Zircaloy and stainless steel is also reported. (See also DP-415.) (auth).
Heavy Water Moderated Power Reactors. Progress Report for December 1959
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
At the end of 1959, 25% of the construction and 85% of the firm design of the Heavy Water Components Test Reactor (HWCTR) were complete. Further safeguards analyses of the HWCTR, done with the aid of analog and digital computers, corroberated earlier data which indicated that the reactor is highly self-regulating, and that the safety system should prevent release of radioactivity outside the containment building. Fabrication tests of metallic uranium fuels and preparation of irradiation specimens of swaged uranium oxide fuel tubes continued. A tube of Zircaloy-2-clad U-2 wt.% Zr failed during a low temperature, low pressure irradiation test to modest exposure. Preliminary examinations of tubular metallurgical joints between Zircaloy and stalnless steel were promising. (For preceding period see DP-445.) (J.R.D.).
Author: L. Isakoff