Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 424
Book Description
Oak Ridge National Laboratory Master Analytical Manual
Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 424
Book Description
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 424
Book Description
Manual of the Analytical Methods Used by the Control Laboratory at the Chemical Processing Plant
Author: M. J. Shepherd (Jr)
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 410
Book Description
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 410
Book Description
Nuclear Science Abstracts
Supplement No. 1 to Manual of the Analytical Methods Used by the Control Laboratory at the Chemical Processing Plant. Parts I and II
Author: M. J. Shepherd (Jr.)
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 172
Book Description
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 172
Book Description
TID.
Master Analytical Manual: Process methods
Author: Oak Ridge National Laboratory. Analytical Chemistry Division
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 996
Book Description
Publisher:
ISBN:
Category : Analytical chemistry
Languages : en
Pages : 996
Book Description
Nuclear Science Abstracts
SCI & TECH TRIBUTYL PHOSP SYNTH PROP REACT ANALYS
Author: Schulz
Publisher: CRC Press
ISBN:
Category : Science
Languages : en
Pages : 362
Book Description
Vol. 2: editors, Wallace W. Schulz, James D. Navratil, Teresa Bess.
Publisher: CRC Press
ISBN:
Category : Science
Languages : en
Pages : 362
Book Description
Vol. 2: editors, Wallace W. Schulz, James D. Navratil, Teresa Bess.
Reprocessing of Irradiated Fission Reactor Fuel and Breeding Materials
Feed Materials
Author:
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 120
Book Description
'Feed materials' refers to U metal, fabricated into fuel elements but not clad, and UF6, both normal isotopic content, suitable for introduction into Pu-production reactors or gaseous diffusion cascades.
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 120
Book Description
'Feed materials' refers to U metal, fabricated into fuel elements but not clad, and UF6, both normal isotopic content, suitable for introduction into Pu-production reactors or gaseous diffusion cascades.