Search engine for discovering works of Art, research articles, and books related to Art and Culture
ShareThis
Javascript must be enabled to continue!

The Plutonium Temperature Effect Program

View through CrossRef
Various theoretical studies have shown that highly diluted plutonium solutions could have a positive temperature effect, but up to now, no experimental program has confirmed this effect. The French Plutonium Temperature Effect Experimental Program (or PU+ in short) aims to effectively show that such a positive temperature effect exists for diluted plutonium solutions. The PU+ experiments were conducted in the “Apparatus B” facility at the CEA VALDUC research center in France. It involved several sub-critical approach type experiments using plutonium nitrate solutions with concentrations of 14.3, 15, and 20 g/l at temperatures ranging from 20 to 40 °C. Fourteen (five at 20 g/l, four at 15 g/l, and five at 14.3 g/l) phase-I experiments (consisting in independent subcritical approaches) were performed between 2006 and 2007. The impact of the uncertainties on solution acidity and plutonium concentration made it difficult to demonstrate the positive temperature effect, requiring an additional phase-II experiment (with a unique plutonium solution) from 22 to 28 °C, that were performed in July 2007. This phase-II experiment has shown the existence of a positive temperature effect of ~ +2.2 pcm/°C (from 22 to 28 °C for a plutonium concentration of 14.3 g/l). It has been recently possible to confirm the results of this program with MORET 5 calculations by generating thermal scattering data S(α,β) at the correct experimental temperatures.
Title: The Plutonium Temperature Effect Program
Description:
Various theoretical studies have shown that highly diluted plutonium solutions could have a positive temperature effect, but up to now, no experimental program has confirmed this effect.
The French Plutonium Temperature Effect Experimental Program (or PU+ in short) aims to effectively show that such a positive temperature effect exists for diluted plutonium solutions.
The PU+ experiments were conducted in the “Apparatus B” facility at the CEA VALDUC research center in France.
It involved several sub-critical approach type experiments using plutonium nitrate solutions with concentrations of 14.
3, 15, and 20 g/l at temperatures ranging from 20 to 40 °C.
Fourteen (five at 20 g/l, four at 15 g/l, and five at 14.
3 g/l) phase-I experiments (consisting in independent subcritical approaches) were performed between 2006 and 2007.
The impact of the uncertainties on solution acidity and plutonium concentration made it difficult to demonstrate the positive temperature effect, requiring an additional phase-II experiment (with a unique plutonium solution) from 22 to 28 °C, that were performed in July 2007.
This phase-II experiment has shown the existence of a positive temperature effect of ~ +2.
2 pcm/°C (from 22 to 28 °C for a plutonium concentration of 14.
3 g/l).
It has been recently possible to confirm the results of this program with MORET 5 calculations by generating thermal scattering data S(α,β) at the correct experimental temperatures.

Related Results

Computational model and physical and technical factors determining the plutonium proliferation resistance
Computational model and physical and technical factors determining the plutonium proliferation resistance
Since the closed nuclear fuel cycle suggests that plutonium is extracted from irradiated fuel and is recycled in nuclear reactors as part of the loaded fuel, proliferation resistan...
Plutonium and Plutonium Compounds
Plutonium and Plutonium Compounds
AbstractThe discovery of plutonium, its economic and military importance, sources, production, and nuclear properties are reviewed. The economic aspects of weapons‐grade and reacto...
Thermal conductivity of mixed oxide fuel (MOX) : effect of temperature, elementary chemical composition, microstructure and burn-up in reactor
Thermal conductivity of mixed oxide fuel (MOX) : effect of temperature, elementary chemical composition, microstructure and burn-up in reactor
Conductivité thermique du matériau combustible nucléaire (U,Pu)O₂ : prise en compte de la température, de la composition élémentaire chimique, de la microstructure et du taux de co...
Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
Feasibility Study of Thorium-Plutonium Mixed Oxide Assembly In Light Water Reactors
AbstractThorium-plutonium mixed oxide, (Th,Pu)OX, is currently used as an alternative fuel in the light water reactors in the world. The main objective of this paper is not only to...
Quantitative evaluation of the plutonium proliferation resistance
Quantitative evaluation of the plutonium proliferation resistance
The mathematical model presented in (Kulikov et al. 2018) can be used for the quantitative evaluation of the plutonium proliferation resistance. This requires the warm-up process o...
An advanced purex process based on salt-free reductants
An advanced purex process based on salt-free reductants
Abstract An advanced plutonium and uranium recovery process has been established based on two organic reductants, N,N-dimethylhydroxylamine (DMHAN) and methylhydrazi...

Back to Top