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|a (TOE)ost1340526
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|a (TOE)1340526
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|a TOE
|c TOE
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|a GDWR
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|a E 1.99:anl/ne--16/23
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|a E 1.99:anl/ne--16/23
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|a anl/ne--16/23
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|a FY16 Status Report on NEAMS Neutronics Activities
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Office of the Assistant Secretary for Nuclear Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
|c 2016.
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| 300 |
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|a 82 p. :
|b digital, PDF file.
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| 336 |
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|a text
|b txt
|2 rdacontent.
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| 337 |
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|a computer
|b c
|2 rdamedia.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
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|a Published through SciTech Connect.
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| 500 |
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|a 09/30/2016.
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| 500 |
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|a "anl/ne--16/23"
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| 500 |
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|a "130821"
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| 500 |
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|a C. H. Lee; E. R. Shemon; M. A. Smith; Y. S. Jung.
|
| 520 |
3 |
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|a The goal of the NEAMS neutronics effort is to develop a neutronics toolkit for use on sodium-cooled fast reactors (SFRs) which can be extended to other reactor types. The neutronics toolkit includes the high-fidelity deterministic neutron transport code PROTEUS and many supporting tools such as a cross section generation code MC<sup>2</sup>-3, a cross section library generation code, alternative cross section generation tools, mesh generation and conversion utilities, and an automated regression test tool. The FY16 effort for NEAMS neutronics focused on supporting the release of the SHARP toolkit and existing and new users, continuing to develop PROTEUS functions necessary for performance improvement as well as the SHARP release, verifying PROTEUS against available existing benchmark problems, and developing new benchmark problems as needed. The FY16 research effort was focused on further updates of PROTEUS-SN and PROTEUS-MOCEX and cross section generation capabilities as needed.
|
| 536 |
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|b AC02-06CH11357.
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| 650 |
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7 |
|a Cross Sections.
|2 local.
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| 650 |
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7 |
|a Fast Reactors.
|2 local.
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| 650 |
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7 |
|a P Codes.
|2 local.
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| 650 |
|
7 |
|a S Codes.
|2 local.
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| 650 |
|
7 |
|a Sodium Cooled Reactors.
|2 local.
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| 650 |
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7 |
|a Neutron Transport.
|2 local.
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| 650 |
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7 |
|a Nuclear Data Collections.
|2 local.
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| 650 |
|
7 |
|a Mesh Generation.
|2 local.
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| 650 |
|
7 |
|a Conversion.
|2 local.
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| 650 |
|
7 |
|a Specific Nuclear Reactors And Associated Plants.
|2 edbsc.
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| 650 |
|
7 |
|a Nuclear Disarmament, Safeguards, And Physical Protection.
|2 edbsc.
|
| 710 |
2 |
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|a Argonne National Laboratory.
|4 res.
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| 710 |
1 |
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|a United States.
|b Office of the Assistant Secretary for Nuclear Energy.
|4 spn.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
|
| 856 |
4 |
0 |
|u http://www.osti.gov/scitech/biblio/1340526
|z Online Access (via OSTI)
|
| 907 |
|
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|a .b90392528
|b 03-09-23
|c 02-15-17
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| 998 |
|
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|a web
|b 05-17-19
|c f
|d m
|e p
|f eng
|g
|h 0
|i 3
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| 956 |
|
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|a Information bridge
|
| 999 |
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|i 566e5e48-9983-53e1-8283-1bd804ee0244
|s b477f080-3c8e-59ee-8d06-771c6dd940ee
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:anl/ne--16/23
|h Superintendent of Documents classification
|i web
|n 1
|
