Topic
GLEEP
About: GLEEP is a research topic. Over the lifetime, 8 publications have been published within this topic receiving 60 citations. The topic is also known as: Graphite Low Energy Experimental Pile.
Papers
TL;DR: In this article, the flux density at the sample position of the A.R.E. reactor GLEEP has been calculated from the activation produced in gold and in manganese-nickel foils.
Abstract: The flux density at the sample position of the A.E.R.E. reactor GLEEP has been calculated from the activation produced in gold and in manganese-nickel foils. The 4πβ-γ coincidence technique is shown to be applicable to the absolute measurement of 56 Mn in foils in spite of the complexity of the decay scheme. The flux density is estimated at 1·663 × 10 8 n/cm 2 /sec per μA of ionization current in the monitor chamber. Efforts are being made to investigate possible variations in the flux/current ratio.
28 citations
TL;DR: A direct measurement of the graphite absorption cross section has been made in the Physical Constants Testing Reactor (PCTR) as discussed by the authors, where the sample tested was reactor grade (GBF) graphite, and had a 2200 m/se
Abstract: A direct measurement of the graphite absorption cross section has been made in the Physical Constants Testing Reactor (PCTR). The sample tested was reactor grade (GBF) graphite, and had a 2200 m/se...
7 citations
1 Jun 1956
TL;DR: The capture cross section of natural boron for slow neutrons has been measured by a dynamic method, in which the decay constant of neutrons in a water tank was plotted against the concentration of added borax as discussed by the authors.
Abstract: The capture cross section of natural boron for slow neutrons has been measured by a dynamic method, in which the decay constant of neutrons in a water tank was plotted against the concentration of added borax. Samples were compared with a standard boron oxide in GLEEP at the Atomic Energy Research Establishment, Harwell. The result is quoted as ?B=760?3 barns for the A.E.R.E. sample of natural boron oxide.
7 citations
TL;DR: Reference thermal and epithermal neutron flux densities have been determined at the GLEEP reactor at AERE Harwell for the slow neutron calibration of film disometers, critically lockets and other detectors as discussed by the authors.
6 citations
TL;DR: The U.K. research nuclear power stations as mentioned in this paper have a number of high-flux nuclear cores, such as GLEEP, BEPO, DIMPLE, and ZEPHYR, with a flux of 1014 n cm-2 s-1.
Abstract: A brief description is given of the U.K. research reactors. Five are in operation at present and four more are in process of being constructed. They are: GLEEP, a low flux natural uranium graphite-moderated reactor; BEPO, a medium flux natural uranium graphite-moderated reactor; DIMPLE, a low flux heavy-water-moderated reactor, designed to take a variety of core arrangements. The remaining two reactors already operating are fast reactors. These are: ZEPHYR, a plutonium fuelled reactor and ZEUS, a 235U fuelled reactor. The four reactors being built are all thermal reactors. Three use heavy-water moderation, and are designed to give a flux of 1014 n cm-2 s-1. The fourth is natural-water moderated of the "swimming-pool" type, and should give a flux of 1012 n cm-2 s-1. These four reactors will all be fuelled with uranium 235. The uses of these reactors are listed and a description of some of the more important uses is presented. In particular the effect of radiation on chemical reactions is receiving considerable attention. In the reactor technology field, work in high-flux reactors is essential and this is taking the form of so-called "loop tests." These are small sections of proposed reactor cores built into research reactors and cooled by a separate circuit.
2 citations
Related Topics (5)
Performance Metrics
| Year | Papers |
|---|---|
| 1979 | 1 |
| 1965 | 1 |
| 1963 | 1 |
| 1961 | 1 |
| 1960 | 2 |
| 1956 | 2 |