origen-arp program (OriGene)
90
Structured Review
OriGene
origen-arp program
Origen Arp Program, supplied by OriGene, used in various techniques. Bioz Stars score: 90/100, based on 1 PubMed citations. ZERO BIAS - scores, article reviews, protocol conditions and more
https://www.bioz.com/product/origen-arp+program/origen+arp+program/10__1016_slash_j__net__2024__05__027-89-25-25
Average 90 stars, based on 1 article reviews
Origen Arp Program, supplied by OriGene, used in various techniques. Bioz Stars score: 90/100, based on 1 PubMed citations. ZERO BIAS - scores, article reviews, protocol conditions and more
https://www.bioz.com/product/origen-arp+program/origen+arp+program/10__1016_slash_j__net__2024__05__027-89-25-25
Average 90 stars, based on 1 article reviews
origen-arp program - by Bioz Stars,
2026-10
90/100 stars
Images
Related Articles
other:Article Title: DEVELOPMENT OF GEOLOGICAL DISPOSAL SYSTEMS FOR SPENT FUELS AND HIGH-LEVEL RADIOACTIVE WASTES IN KOREA Article Snippet: The decay heat from the reference PWR spent fuel (Table 3) is calculated using the Article Title: Preliminary conceptual design of a geological disposal system for high-level wastes from the pyroprocessing of PWR spent fuels Article Snippet: The inventories of spent fuels are linearly dependent on the production of electricity generated by nuclear energy.. Pyroprocessing of PWR spent fuels is one of promising technologies which can reduce the volume of spent fuels remarkably.. The properties of high-level wastes from the pyroprocessing are totally different from those of spent fuels. Article Title: Estimating spent fuel burnup with Neutron measurements: A Practical Rule of Thumb Equation Article Snippet: At 80 different data points, six TNSI values corresponding to cooling times of 5, 10, 20, 30, 50, and 60 years were computed using the Article Title: A fuel for generation IV nuclear energy system: Isotopic composition and radiation characteristics. Article Snippet: This paper reports on an important issue of designing appropriate nuclear fuel of a hightemperature gas-cooled nuclear reactor operating in a thorium-plutonium nuclear fuel cycle.. The neutronic calculations for a fuel of specific isotopic composition were performed before the analyses were done on the alpha emission probabilities, and on the neutron and photon sources as a result of (α,n) reaction.. The main focus was on the quantitative evaluation of the neutron yield and the neutron energy spectrum for the generated neutrons through (α,n) reaction on light nuclei of dispersed nuclear fuel. |