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ANP PROJECT QUARTERLY PROGRESS REPORT<br />

CF-52-8 - 120<br />

Y-F30-8<br />

CF-52-9-99<br />

CF-52-9-145<br />

CF-5 2 -9 - 16 1<br />

CF-52-11-143<br />

OIWL- 1217<br />

ORNL- 1438<br />

CF-52-8 - 38<br />

CF-52-10-9<br />

CF-52- 11- 124<br />

Y-889<br />

(3-52-8-163<br />

CF-52-8-212<br />

CF-52-9 - 20 1<br />

CF-52 -9 - 20 2<br />

CF-52 - 11-72<br />

CF-52 - 11 - 10 3<br />

CF- 5 2 - 11 - 10 4<br />

CF-52- 11- 105<br />

CF-52-11-106<br />

CF-52 - 11- 113<br />

OWL- 1342<br />

OWL- 139 5<br />

2 00<br />

Aircraft Shield Analysis W. L. Wilson<br />

A. I,. Walker<br />

Radiation Through <strong>the</strong> Control Rod Pene- H. L. F. Enlund<br />

trations of <strong>the</strong> ARE Shield<br />

Neutron to Gamma Ray Ratio Experiments<br />

J. L. Meern<br />

Biolo ical Experimentation in Support of J. Furth<br />

ANP froject The Development of Lead-Impregnated Moulding E. P. Blizard<br />

and Modeling Materials for Shielding of<br />

Penetrating Radiations<br />

Basic Shielding Research<br />

Neutron Transmission Through Air Fil<br />

Ducts<br />

Determination oE <strong>the</strong> Power of <strong>the</strong> Bu<br />

Shielding Reactor, I1<br />

Gamma-Ray Spectral Measurements with<br />

Divided Shield Mockup, Part I11<br />

E. P. Blizard<br />

ed C. E. Clifford<br />

k E. B. Johnson<br />

J. L. Meem<br />

<strong>the</strong> F. C. Maienschein<br />

Summary of Lid Tank Neutron Dosimeter T. V. Rlosser<br />

Measurements in Pure Water<br />

Gamma Ray Spectral Measurements with <strong>the</strong> F. C. Maienschein<br />

Divided Shield Mockup, Part IV<br />

W. Meat Transfer and Physical Properties Research<br />

Selected Physical Properties of Mercury in<br />

<strong>the</strong> Temperature Range 100 to 1000°C. A<br />

Literature Search<br />

Measurement of <strong>the</strong> Thermal Conductivity of<br />

Flinak<br />

Physical Property Charts for Some Reactor<br />

Fuels, Coolants, and Miscellaneous<br />

Materials<br />

Cooling Hole Distribution for Reactor<br />

Reflectors<br />

Heat Generation in a Slab for a Non-Uniform<br />

Source of Radiation<br />

Measurement of <strong>the</strong> Thermal Conductivity of<br />

Fluoride Mixture No. 33<br />

Heat Capacity of Fused <strong>Salt</strong> Mixture No. 21<br />

Heat Capacity of LiOH<br />

Density Measurements of Fuel <strong>Salt</strong>s No. 31<br />

and 33<br />

Viscosity Measurements of Fuel <strong>Salt</strong>s No. 31<br />

and 33<br />

Transient Methods for Determining Thermal<br />

Conductivity of Liquids<br />

Enthalpies and Heat Capacities of Stainless<br />

Steel (316) and Zirconium<br />

Forced Convection Beat Transfer in Pipes<br />

with Volume Heat Sources<br />

F. Sachs<br />

L. Coo er<br />

S. J. 8aliborae<br />

A?dP Physical<br />

Properties<br />

Group, REEDivision<br />

W. S. Farmer<br />

W. S. Farmer<br />

S. J. Claiborne<br />

W. D. Powers<br />

W. D. Powers<br />

R. F. Redmond<br />

T. N. Jones<br />

n. F. Redmond<br />

T. N. Jones<br />

W. B. Harrison<br />

8 -20 -52<br />

9 -25-52<br />

9 - 18 -52<br />

9-24-52<br />

9 -26-52<br />

11-19-52<br />

11- 11-52<br />

(to be issued)<br />

8 -8 -52<br />

10 - 1-52<br />

11-17 -52<br />

7 - 10 - 52<br />

8 -26-52<br />

8 -28 -52<br />

9-3-52<br />

9-4-52<br />

11- 11-52<br />

11-15-52<br />

11- 15 -52<br />

11-15-52<br />

11-15-52<br />

11- 1-52<br />

R. F. Redmond (to be issued)<br />

J. Lones<br />

H. F. Po pendiek (to be issued)<br />

L. D. PaPmer

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