Status of special reactor process tube loadings, December 1, 1968 (open access)

Status of special reactor process tube loadings, December 1, 1968

This report gives the status of production tests control tube loadings in reactor process tubes containing significant amounts of SS material. All data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN 3443.
Date: December 10, 1968
Creator: Walton, R. P.
System: The UNT Digital Library
Status of special reactor process tube loadings, October 1, 1968 (open access)

Status of special reactor process tube loadings, October 1, 1968

This document provides the status of production tests control tube loadings in reactor process tubes containing significant amounts of SS material.
Date: October 10, 1968
Creator: Walton, R. P.
System: The UNT Digital Library
Amended calibration data for XE-2 gamma heating rate sensors (TE882 A, TE884 A, TE885 A, and TE886 A) (open access)

Amended calibration data for XE-2 gamma heating rate sensors (TE882 A, TE884 A, TE885 A, and TE886 A)

This report talks about Amended calibration data for XE-2 gamma heating rate sensors (TE882 A, TE884 A, TE885 A, and TE886 A)
Date: September 10, 1968
Creator: Hoff, R. G.
System: The UNT Digital Library
Forward end cementing development (open access)

Forward end cementing development

None
Date: September 10, 1968
Creator: Brickman, E.L.
System: The UNT Digital Library
Shield element thermal shock test (open access)

Shield element thermal shock test

None
Date: September 10, 1968
Creator: Morgan, L.P.
System: The UNT Digital Library
Status of special reactor process tube loadings, September 1, 1968 (open access)

Status of special reactor process tube loadings, September 1, 1968

This report provides the status of production tests control tube loadings in reactor process tubes containing significant amounts of SS material.
Date: September 10, 1968
Creator: Walton, R. P.
System: The UNT Digital Library
Experiment design for GTR-20 radiation effects test of beryllium, 37/W406 (open access)

Experiment design for GTR-20 radiation effects test of beryllium, 37/W406

None
Date: July 10, 1968
Creator: Burwell, D. L.
System: The UNT Digital Library
Experiment design for GTR-20 radiation effects test of copper--boron-10, 37/ W409 (open access)

Experiment design for GTR-20 radiation effects test of copper--boron-10, 37/ W409

None
Date: July 10, 1968
Creator: Burwell, D. L.
System: The UNT Digital Library
Experiment design for GTR-20 radiation effects test of Inconel-718, 37/ W410, 15/W101, and 15/W202 (open access)

Experiment design for GTR-20 radiation effects test of Inconel-718, 37/ W410, 15/W101, and 15/W202

None
Date: July 10, 1968
Creator: Burwell, D. L.
System: The UNT Digital Library
Experiment design for GTR-20 radiation effects test of shield material, 37/ W411 (open access)

Experiment design for GTR-20 radiation effects test of shield material, 37/ W411

None
Date: July 10, 1968
Creator: Burwell, D. L.
System: The UNT Digital Library
Experiment design for GTR-20 radiation effects test of spot welded titanium bands, 15/W003 (open access)

Experiment design for GTR-20 radiation effects test of spot welded titanium bands, 15/W003

None
Date: July 10, 1968
Creator: Burwell, D. L.
System: The UNT Digital Library
Effective Pu-238 and Np-237 neutron absorption cross sections in N and K Reactors (open access)

Effective Pu-238 and Np-237 neutron absorption cross sections in N and K Reactors

The efficiency of producing Pu-238 from Np-238 depends on the relative absorption cross sections of the target, Np-237, and the product, Pu-238. A lowering of the Pu-238/Np-237 cross section ratio reduces the destruction of Pu-238 formed during reactor operation. The absorption cross sections of both these isotopes are strongly neutron energy dependent; the absorption cross section of Pu-238 decreases more rapidly with thermal neutron temperature increases than the conventional v{sup {minus}1} dependency and exhibits negligible resonance absorption. On the other hand, Np-237 is a very nearly v{sup {minus}1} thermal neutron absorber and has dominant low level resonance cross sections. Thus, for higher thermal neutron temperatures and a more epithermal neutron spectrum, depletion of the Pu-238 product is reduced relative to Np-237 burnout. The relative absorption cross sections of these two isotopes were calculated for the K and N Reactors as a function of graphite temperature for two linear densitie of neptunium in the target elements for each.reactor type. The method of calculation was as follows: The HAMMER integral transport code was used to obtain region and cell averaged four-group cross sections for both the fuel and target cells. These cross sections were then used in the HFN diffusion theory code …
Date: June 10, 1968
Creator: Roblyer, S.P.
System: The UNT Digital Library
Development of preliminary creep data for carbide composites (open access)

Development of preliminary creep data for carbide composites

None
Date: January 10, 1968
Creator: Malarky, J. T.
System: The UNT Digital Library
Status of special reactor process tube loadings, January 1, 1968 (open access)

Status of special reactor process tube loadings, January 1, 1968

This report presents details of the status of special reactor process tube loadings for the month of January 1968.
Date: January 10, 1968
Creator: Walton, R. P.
System: The UNT Digital Library