HEA|  |01531nam  2200289I1 4500
001|  |021997014740
005|  |20050609084947.0
008|  |820224s1977    dcua     b   f00010 eng d
040|  |▼aGPO▼cGPO▼dCWR
043|  |▼an-us－－-
093|  |▼aTL31▼23
100|1 |▼aEpel, Lester G.
245|10|▼aSODEMME :▼ba natural circula-
   |  |tion thermal hydraulics code f-
   |  |or HTGR transient analysis /▼c-
   |  |Lester G. Epel ; prepared for -
   |  |the United States Nuclear Regu-
   |  |laotry Commission, Division of-
   |  | Reactor Safety Research, Offi-
   |  |ce of Nuclear Regulatory Resea-
   |  |rch under contract no. EY-76-C-02-0016.
260|  |▼a[Washington, D.C.] :▼bThe Di-
   |  |vision ;▼aSpringfield, Va. :▼b-
   |  |Available from National Techni-
   |  |cal Information Service,▼c1977.
300|  |▼av, 64 p. :▼bill. ;▼c28 cm.
500|  |▼a"HTGR Safety Evaluation Divi-
   |  |sion, Department of Applied Sc-
   |  |ience, Brookhaven National Lab-
   |  |oratory, Associated Universities, Inc."
500|  |▼a"Date published - August 1977."
500|  |▼a"BNL-NUREG-50682."
504|  |▼aIncludes bibliographical references.
650| 0|▼aGas cooled reactors▼xCooling.
650| 0|▼aHeat▼xTransmission▼xComputer programs.
650| 0|▼aHydraulic circuits▼xComputer programs.
710|2 |▼aU.S. Nuclear Regulatory Comm-
   |  |ission.▼bDivision of Reactor S-
   |  |afety Research.
710|2 |▼aBrookhaven National Laborato-
   |  |ry.▼bHTGR Safety Division.
740|2 |▼aA natural circulation therma-
   |  |l-hydraulics code for HTGR tra-
   |  |nsient analysis.
950|  |▼aJ▼fTL31/E63
999|  |▼tC▼Atshs11▼a20050609 08:45:31-
   |  |▼Mtshs11▼m20050609 08:49:47▼Gt-
   |  |shs11▼g20050609 08:50:20

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