A proposal is given of an approach to a fission-product trapping system which appears feasible on the basis of thermodynamic and other data available. Reactor and trapping conditions are outlined. The half-lives, fission yields, and volatility of the fission products of interest are described. To provide the most effective retention at elevated temperatures, two types of reagents are required: a highly electropositive metal that will not melt or appreciably vaporize and which will form stable non-volatile compounds with non-metallic or near non-metallic fission products; and a reagent to provide a highly electronegative element to form stable, non-volatile compounds with metallic fission products. Thermodynamic properties are included for c...
High-purity, nuclear-grade graphites react very slowly with oxygen and are noncombustible by convent...
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite wa...
Emphasis was shifted in the Pebble Bed Reactor (PBR) Fuel Element Development Program from coatings ...
The transport of fission products from points of origin in unclad graphite matrix-type fuels to the ...
The goal of this project is to determine changes in adsorption and desorption of fission products to...
This publication deals with the basic principles of fission product retention in nuclear plants with...
Evidence concerning high-temperature loss of fissionproduct atoms from U- graphite fuel material is ...
A simple mathematical model was developed to describe the steady-state release rate of gaseous fissi...
The experimental work on the diffusion of fission products in graphite matrices at high temperatures...
Improved graphites for use in fuel elements were developed from artificial graphites and phenolic re...
Graphite elements of nuclear power plants accumulate in time a small amount of uranium, radionuclide...
Results of a study concerned with the problem of retarding the diffusion of fission products through...
The fuel elements of High-Temperature Reactors, coated with pyrolitic carbon and covered with graphi...
Diffusion of xenon captured in graphite by fission recoil has been studied over the wide range of fi...
The chemical problems largely involve gas- and solidphase chemistry where chemical reactions and phy...
High-purity, nuclear-grade graphites react very slowly with oxygen and are noncombustible by convent...
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite wa...
Emphasis was shifted in the Pebble Bed Reactor (PBR) Fuel Element Development Program from coatings ...
The transport of fission products from points of origin in unclad graphite matrix-type fuels to the ...
The goal of this project is to determine changes in adsorption and desorption of fission products to...
This publication deals with the basic principles of fission product retention in nuclear plants with...
Evidence concerning high-temperature loss of fissionproduct atoms from U- graphite fuel material is ...
A simple mathematical model was developed to describe the steady-state release rate of gaseous fissi...
The experimental work on the diffusion of fission products in graphite matrices at high temperatures...
Improved graphites for use in fuel elements were developed from artificial graphites and phenolic re...
Graphite elements of nuclear power plants accumulate in time a small amount of uranium, radionuclide...
Results of a study concerned with the problem of retarding the diffusion of fission products through...
The fuel elements of High-Temperature Reactors, coated with pyrolitic carbon and covered with graphi...
Diffusion of xenon captured in graphite by fission recoil has been studied over the wide range of fi...
The chemical problems largely involve gas- and solidphase chemistry where chemical reactions and phy...
High-purity, nuclear-grade graphites react very slowly with oxygen and are noncombustible by convent...
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite wa...
Emphasis was shifted in the Pebble Bed Reactor (PBR) Fuel Element Development Program from coatings ...