2 Matching Results

Search Results

Advanced search parameters have been applied.

Stationary low power reactor No. 1 (SL-1) accident site decontamination & dismantlement project

Description: The Army Reactor Area (ARA) II was constructed in the late 1950s as a test site for the Stationary Low Power Reactor No. 1 (SL-1). The SL-1 was a prototype power and heat source developed for use at remote military bases using a direct cycle, boiling water, natural circulation reactor designed to operate at a thermal power of 3,000 kW. The ARA II compound encompassed 3 acres and was comprised of (a) the SL-1 Reactor Building, (b) eight support facilities, (c) 50,000-gallon raw water storage tank, (d) electrical substation, (e) aboveground 1,400-gallon heating oil tank, (f) underground 1,000-gallon hazardous waste storage tank, and (g) belowground power, sewer, and water systems. The reactor building was a cylindrical, aboveground facility, 39 ft in diameter and 48 ft high. The lower portion of the building contained the reactor pressure vessel surrounded by gravel shielding. Above the pressure vessel, in the center portion of the building, was a turbine generator and plant support equipment. The upper section of the building contained an air cooled condenser and its circulation fan. The major support facilities included a 2,500 ft{sup 2} two story, cinder block administrative building; two 4,000 ft{sup 2} single story, steel frame office buildings; a 850 ft{sup 2} steel framed, metal sided PL condenser building, and a 550 ft{sup 2} steel framed decontamination and laydown building.
Date: November 1, 1995
Creator: Perry, E.F.
Partner: UNT Libraries Government Documents Department

Decontamination and dismantlement of the old hot laundry, CFA-669. Final report

Description: This final report describes the decontamination and dismantlement (D&D) of the old hot laundry, located at the Idaho National Engineering Laboratory (INEL) Central Facilities Area (CFA). The report describes the site before and after D&D, processes used, cost and duration, and waste volume generated. In addition, lessons learned are presented. Pre-D&D characterization indicated gross alpha concentrations in the building ranged from 6 to 310 pCi/g and gross beta measurements from 6 to 15,000 pCi/g. Gamma spectrum analysis identified cobalt-60, cesium-137, antimony-125, europium-152, europium-154, and niobium-94.
Date: January 1, 1995
Creator: Smith, D.L. & Perry, E.F.
Partner: UNT Libraries Government Documents Department