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limit:

The maximum number of results to return

offset:

The offset of the first result

link:

Show values as links

headers:

Display the headers/property names

mainlabel:

The label to give to the main page name

intro:

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To embed this query inline into a wiki page use the code below.

{{#ask: [[Project::TAC:ME1797]]
 |?Issue date
 |?From
 |?Title
 |?Project stage
 |format=table
 |limit=50
 |offset=0
 |sort=
 |order=asc
 |mainlabel=
 |searchlabel=[Table View]
}}

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Query log

{
    "query_string": "[[Project::TAC:ME1797]]",
    "query_source": "SMWSQLStore",
    "query_time": "0.0644",
    "from_cache": false
}

	Issue date	From	Title	Project stage
ML092120053	5 August 2009	Peter Bamford Plant Licensing Branch I	Individual Plant Actions Pressurized-water Reactor Owners Group Topical Report BAW-2374, Revision 2, Risk-Informed Assessment of Once-Through Steam Generator Tube Thermal Loads Due to Breaks in Reactor Coolant System.	Other
ML093010455	3 November 2009	Peter Bamford Plant Licensing Branch I	Once-Through Steam Generator Tube Loads Under Conditions Resulting from Postulated Breaks in Reactor Coolant System Upper Hot-Leg Large-Bore Piping	Other
TMI-09-105, Response to June 25, 2009, Public Meeting Between the U.S. Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG) Related to PWROG Topical Report BAW-2374, Revision 2	4 September 2009	Exelon Cowan P	Response to June 25, 2009, Public Meeting Between the U.S. Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG) Related to PWROG Topical Report BAW-2374, Revision 2	Meeting
TMI-10-004, Summary of Analysis Results to PWROG Topical Report BAW-2374, Revision 2	29 January 2010	Exelon David Helker	Summary of Analysis Results to PWROG Topical Report BAW-2374, Revision 2	Other

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