REACTOR TECHNOLOGY REPORT NO. 11-PHYSICS
Reactor Theory: A series of measurements of spatial flux transients introduced by hydrogenous gaps; and absorbing slabs was made in the PPA. A few- group theory of water gap peaking is presented and compared with flux transient experiments. A method was developed in which diffusion theory and existing nuclear codes are utilized for the prediction of gamma energy distribution in reactor cores. SWAKRAUM a two-region thermal space-energy code for the IBM-704, is described and calculations for the spatially dependent thermal spectrum near an interface between different media are compared with experiment. TRAnvAR, a one-velocity slab geometry code for the calculation of certain space-energy problems, was generalized to permit up and down scattering in hydrogen. The problem is solved in two steps At first, the one-velocity problem is solved when sources are assumed to be present in N distinct moderator slabs. The spectrum is next found by solving the coupled set of integral equations obtained when the source in each moderator region is expressed as an integral of the fluxes at different energies. The effects of chemical binding of molecules on the slowing down time of neutrons in water were investigated. Experimental Physics: Water- gap reactivity effects as a function of temperature were measured in highly enriched cores using the pressurized critical facility at KAPL and were compared with results of Two-dimensional diffusion-theory calculations. A series of measurements of the core distributed reactivity coefficients of moderator and structural materials was made in a CH,-moderated and -reflected slab reactor (PMA-6) The experiments were analyzed by means of various cross-section routines currently employed in nuclear design studies. Temperature coefficients were obtained from measurements made on 10 different cores and reflectors of the Pressurized Test Reactor. The critical temperature, temperature coefficient, and neutron density distribution were determined in the region from 68 to 550 deg F of an 8 x 30 x 32 in. core having various wt.% B/sup 10/stainless steel septa. The temperature dependence of plate equivalents for burnable poison pin arrays was investigated by a direct comparison technique in the PTR. Experiments described in this paper were conducted with critical reactors covering a wide range of metal-to-water ratios, temperatares, loadings, and sizes and of very simple structure and geometry. Cross Sections: Reactor spectra effects on fission fragment cross sections were investigated. A measurement of the resonance integral of Zr/sup 91/ was made on a 4 gm sample of ZrO/sub 2/. Magnesiunn cross sections were prepared for use as input for the MUFT code. Work on the influence of cross sections upon calculated neutron age and reactor criticality was undertaken in order to develop an understanding of Zr cross sections and to determine whether the usual computational techniques masked the effects of strong scattering resonances in O and Zr. Crose section values are given for Sm Eu, and Gd. Burnable Poisons: Measurements are reported on the burnup of Eu and Dy under neutron irrndiation in the form of Dy/sub 2/O/sub 3/ and Eu/sub 2/O/sub 3/ powder. The ratio of the amount of Eu/sup 152*/ (9.2 hr) to Eu/sup 152/ (11 yr) produced under neutron irradiation of Eu/sup 151/ was measured. The particle self-shielding of boron carbide was investigated. Mathematical Theory and Methods: Work on advanced diffusion theory techniques, alternatingdirection-implicit iteration technique, and code development is summarized. (For preceding period see KAPL 200-4.) (W.D.M.)
- Research Organization:
- Knolls Atomic Power Lab., Schenectady, N.Y.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-14-006754
- OSTI ID:
- 4201461
- Report Number(s):
- KAPL-2000-8
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ABSORPTION- GROUP THEORY- HYDROGEN- MEASURED VALUES- - NEUTRON FLUX- NEUTRONS- PLATES- PPA- REACTORS- SPACE- TRANSIENTS- ZONES
BARRIERS- DENSITY- DISTRIBUTION- NEUTRON FLUX- REACTOR CORE- STAINLESS STEELS- TEMPERATURE
BORON CARBIDES- PARTICLES- SHIELDING
CARBON HYDRIDES- CONFIGURATION- CROSS SECTIONS- DISTRIBUTION- MEASURED VALUES- MODERATORS- PLANNING- REACTIVITY- REACTOR CORE- REACTORS- REFLECTORS
COMPUTERS- ENERGY- NEUTRONS- NUMERICALS- PROGRAMMING- SPACE- SPECTRA- SURFACES- THERMAL NEUTRONS- ZONES
CONFIGURATION- METALS- REACTOR FUELING- REACTORS- TEMPERATURE- WATER
CRITICALITY- CROSS SECTIO