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Technical studies supporting IPD disaster planning
A study was undertaken of means for rendering the plant less vulnerable to self-destruction with radioactive contamination spread. It was concluded that the only course of action was to totally discharge the reactors and provide water cooling flow by gravity to the reactor storage basins. This report reviews the technical considerations involved in determining the feasibility of the course of action with emphasis on assuring basin integrity.
Date:
August 5, 1963
Creator:
Carlson, P. A. & Jaske, R. T.
System:
The UNT Digital Library
Development Test IP-556-D, supplement A, irradiation service request HAPO-278 outgassing rate of tritium at high temperature
The nuclear heat generation rate in the first capsule irradiated was higher by a factor of two than was calculated. The original capsule was irradiated in a dry bore with cooling water in the annulus only. The new capsule will be irradiated in a water-cooled bore facility with additional cooling coils around the lithium containing tube. This will keep the inner capsule temperature below 150 C during the initial tritium buildup period prior to outgassing. This Supplement authorizes the irradiation of an additional capsule and the removal of the present facility and installation of a single tube general purpose facility. All remaining provisions of the original development test are in force except for minor exceptions due to the water flow in the bore which have been changed in the following writeup.
Date:
July 5, 1963
Creator:
DeMers, A. E.
System:
The UNT Digital Library
The Irradiation of Six Unclad BeO Base Fuel Elements in the LITR, and Failure of the C-48 Facility Tube
None
Date:
September 5, 1963
Creator:
Elkins, J. D.
System:
The UNT Digital Library
Results of production test IP-528-I, Supplement A: B and D Reactors` high tank drawdown test
Recent high tank drawdown data obtained at F reactor during periodic high velocity flushes indicated a reduction in flow to the reactor due to building of corrosion products in the high tank discharge lines. The apparent flow reduction at F reactor was verified by conducting a high tank drawdown test. Visual inspection of B, D, and F high tank discharge lines revealed comparable densities of corrosion product buildup, and high tank drawdown data during high velocity flushes at B and D also indicated a reduction in flow. High tank flow rate to the reactor under simulated emergency conditions needed to be accurately determined to establish current backup adequacy. This report presents the results of the tests which were conducted at D reactor on January 20, 1963 and at B reactor on February 11, 1963.
Date:
June 5, 1963
Creator:
Hollifield, P. J. & Zimmerman, P. J.
System:
The UNT Digital Library
Results of aquifer tests at hydrologic test sites 1 and 2, Tatum Dome, Lamar County, Mississippi
None
Date:
April 5, 1963
Creator:
Koopman, F. C.; Johnson, A. I.; Armstrong, C. A. & Taylor, R. E.
System:
The UNT Digital Library
Production test IP-638-D, operation of KER-1 -2, -3, and -4 simulating N reactor conditions December 5, 1963
The objective of this production tests is to irradiate N Reactor prototype and candidate fuel components and alternate products at simulated N-Reactor pressure and temperature conditions in KER Loops 1, 2, 3, and 4.
Date:
December 5, 1963
Creator:
Neidner, R.
System:
The UNT Digital Library
Thermal Analysis of the SNAP 6 Reactor
None
Date:
August 5, 1963
Creator:
Steele, L. R.
System:
The UNT Digital Library
Operating limits -- Hanford Production Reactors
This document provides Operating Limits which shall be applicable to the eight production reactor facilities, designated B, C, D, DR, F, H, KE and KW (hereinafter referred to as the Hanford Production Reactors) located at the Hanford site.
Date:
November 5, 1963
Creator:
unknown
System:
The UNT Digital Library