1993年9月1日 · This report deals with the mechanical separation aspects concerning physical disassembly of the FSV graphite fuel element into the empty graphite fuel blocks and fuel compacts. This report recommends that a drilling technique is the preferred choice for accessing the, fuel channel holes and that each hole is drilled separately.

safety hazard at FSV. Structural or Graphite Failures Routine inspections discovered superficially cracked fuel element webs that were not considered a safety issue at FSV. Corroded prestressed concrete reactor vessel tendon wires also did not present any undue safety hazards to …

FSV ISFSI SAR Revision 8 3-1 3. PRINCIPAL DESIGN CRITERIA 3.1. Purpose of Installation The MVDS system is used for the interim storage of FSV HTGR fuel on the DOE owner controlled property at the FSV site and is operated as a stand-alone facility. The MVDS system provides storage for six segments of the HTGR fuel (1,464 fuel elements). The fuel is

1982年9月2日 · The FSV core assembly [1,2] The FSV core is described in detail to enable an understanding of its assembly, most especially the pur- poseful downward bypass flows and the allowable cross flows, which are the prime contributors to the fluctua- tion phenomenon. ... The core support blocks are each sup- ported by 3 graphite posts with the top ends ...

2004年1月1日 · Second, the moisture can cause corrosion of the PGX graphite core support post. The FSV UFSAR 11. ... The core support posts are ATJ graphite and the permanent side reflectors are HLM graphite.

1993年9月1日 · One of the alternatives to the disposal of the Fort St. Vrain (FSV) reactor spent nuclear fuel involves the separation of the fuel rods composed of compacts from the graphite fuel block assembly. After the separation of these two components, the empty graphite fuel blocks would be disposed of as a low level waste (provided the appropriate requirements are met) and the fuel compacts would be ...

1991年1月1日 · Generally, good graphite performance in FSV. Excellent fission product retention with these coatings. Good FSV performance with these purifica- tion system components. Primary and secondary containment is PCRV at FSV. * MHTGR primary and secondary containment includes fuel particle coatings and steel pressure vessel, respectively.

The Safety Analysis Report (SAR) evaluates the use of H-451 graphite in future reload segments for the Fort St. Vrain (FSV) Nuclear Generating Station. It is proposed to replace the reference core H-327 graphite fuel and replaceable reflector elements with H-451 graphite elements as each segment is reloaded.

1993年9月1日 · Part of Fort St. Vrain (FSV) and most of the Peach Bottom (PB) reactor spent fuels are currently stored at INEL and may remain in storage for many years before disposal. Three disposal pathways have been proposed: intact disposal, fuels partially disassembled and the high-level waste fraction conditioned prior to disposal, and fuels completed disassembled and conditioned prior to disposal.

a system of three graphite dowels located on the top face of each element. The bottom side of each fuel block features three dowel sockets for interlocking with the block underneath. These dowels are not simulated in the MCNP model. Table 2 and Table 3 provide the material compositions of the FSV fuel and graphite block, respectively.