The physics design of a high flux core for the R-5 reactor
Description
In the second phase of operation of the R-5 reactor, there has been a proposal to obtain higher fluxes by loading Pu-Al alloy fuels into the central region of the core. The constraints that have been laid down for the design of this core are the following: (a) the specific power in a natural uranium 28 rod cluster of the Pickering type should be 34 KW/Kg when irradiated in the central loop of the R-5 reactor. (With the present core one gets 15 KW/Kg.), (b) the total power of the reactor should not exceed 100 MW, (c) the fuel channels in the outer zone should not produce more than their rated power, and (d) the total quantity of Pu produced by conversion of uranium-238 in the natural uranium channels should not be less than the total amount of Pu burnt in the Pu-Al alloy fuels in the same length of time. Physics studies have established the feasibility of meeting these four constraints at the beginning of core life and have also provided a fuelling scheme which enables the high flux to be maintained with a reasonable rate of refuelling. The results are presented. (author)
Additional details
Publishing Information
- Publisher
- Department of Atomic Energy.
- Imprint Place
- Bombay
- Imprint Title
- Proceedings of the symposium on reactor physics [held at Bombay during] March 1-3, 1976
- Journal Page Range
- p. 304-307.
Conference
- Title
- Symposium on reactor physics.
- Dates
- 1 - 3 Mar 1976.
- Place
- Bombay, India.
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 10480717
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL CHANNELS; FUEL MANAGEMENT; NATURAL URANIUM; NEUTRON FLUX; NUCLEAR FUELS; NUCLEAR POWER; PHWR TYPE REACTORS; PLUTONIUM ALLOYS; REACTOR CORES; TROMBAY R-5 REACTOR
- Descriptors DEC
- ACTINIDE ALLOYS; ACTINIDES; ALLOYS; ELEMENTS; ENERGY SOURCES; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; MANAGEMENT; METALS; NATURAL URANIUM REACTORS; NUCLEAR MATERIALS MANAGEMENT; POWER; RADIATION FLUX; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST REACTORS; THERMAL REACTORS; URANIUM