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Idaho National Laboratory Cultural Resource Management Plan

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The Loss of Fluid Test (LOFT) program was<br />

first conceptualized in 1962, shortly after the<br />

demise of the ANP, but underwent an extensive<br />

series of modifications before actual testing began<br />

at TAN in 1976. LOFT consisted of a series of<br />

simulated loss-of-coolant accidents. In 1978, the<br />

first nuclear tests began at the LOFT containment<br />

facility. The LOFT reactor was the only nuclear<br />

reactor in the world capable of repeatedly<br />

simulating loss-of-coolant incidents similar to<br />

those that might occur in commercial power<br />

reactors. In 1979, the LOFT scientists and reactor<br />

played a vital role in predicting activity within the<br />

Three Mile Island (TMI) reactor core as scientists<br />

struggled to manage and control the TMI reactor<br />

core meltdown. Successful testing continued at<br />

LOFT until 1982, when an international<br />

consortium took over operations and continued<br />

testing until 1986, when the program officially<br />

ended. The Water Reactor Research Test Facility<br />

(WRRTF), originally constructed to house reactor<br />

shielding tests associated with the ANP program,<br />

was reused during the LOFT program to conduct<br />

nonnuclear simulations of thermal-hydraulic<br />

features of commercial nuclear reactors. After a<br />

long history of significant contributions to nuclear<br />

science and engineering, many structures<br />

associated with LOFT and other, less significant<br />

programs now lack missions and have been<br />

vacated and demolished (INEL 1969; Stacy 1994)<br />

(see Figure 22).<br />

Figure 22. Demolition of the WRRTF stack.<br />

<strong>Idaho</strong> Nuclear Technology and<br />

Engineering Center. In 1953, INL’s most<br />

important reactor support facility, the INL area<br />

now known as INTEC (formerly the <strong>Idaho</strong><br />

Chemical Processing <strong>Plan</strong>t [ICPP] 3 ), began the<br />

process of recovering and reprocessing unburned,<br />

enriched uranium from “spent” reactor fuel<br />

elements. INTEC was initially designed and built<br />

as a five-year demonstration facility, but the Cold<br />

War nuclear arms race led to an increased demand<br />

for nuclear fuel, and INTEC soon became a<br />

full-scale production facility (see Figure 23).<br />

Figure 23. Aerial view of INTEC.<br />

Spent reactor fuel elements were transported<br />

to INTEC to extract enriched uranium, which was<br />

then shipped to another national laboratory at<br />

Savannah River, South Carolina, for use as fuel in<br />

reactors producing plutonium and tritium for<br />

nuclear weapons.<br />

In addition to its groundbreaking work in fuel<br />

reprocessing technology, INTEC became a leader<br />

in the development of new technologies to manage<br />

nuclear wastes.<br />

The Waste Calcining Facility (WCF),<br />

developed at INTEC in the mid-1950s,<br />

transformed highly acidic radioactively<br />

contaminated liquid wastes into granular pellets<br />

that are much safer and easier to store until<br />

radioactive components in the waste are rendered<br />

safe through natural decay. INTEC calcining<br />

operations continued after WCF closure with its<br />

successor, the New Waste Calcining Facility<br />

(NWCF). Although fuel reprocessing at INTEC<br />

ended in 1992 and the final waste calcining<br />

campaign occurred in June 2000, their<br />

contributions to the history of nuclear science have<br />

been significant. (INEL 1969; Pace and Braun<br />

2000; Stacy 1997).<br />

3. Unless otherwise specified for historical purposes, the<br />

INL area originally known as ICPP is primarily referred<br />

to in this section by its current designation of INTEC.<br />

32

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