| 1 |
GAMD-304
Fission product traps for use in high-temperature gas-cooled graphite reactors / Zumwalt, L.R.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1958.3.13
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| 2 |
GAMD-702
HTGR fission-product trapping system--preliminary system analysis and summary of factors / Pigford, T.H.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp . , 1959.2.24
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| 3 |
GAMD-788
A thermal mock-up of an irradiation capsule / Palmer, L.D.
San Diego, CA (USA) : General Atomic Div. General Dynamics Corp. , 1959.5.12
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| 4 |
GAMD-878
Recent developments in graphite / Kosiba, W.L.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.7.17
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| 5 |
GAMD-960
KINETIC LIMITATIONS TO CARBON DEPOSITION
, 1959
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| 6 |
GAMD-960
Kinetic limitations to carbon deposition / Ragone, D.V.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.9
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| 7 |
GAMD-984
Shutdown heat generation in HTGR / Morse, D.C.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.9.16
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| 8 |
GAMD-1049
Simplified method for core thermal design / Rogers, J.T.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.11.17
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| 9 |
GAMD-1050
Epithermal absorption by control rods of variable blackness / Devooght, J.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.10.12
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| 10 |
GAMD-1078
Approximate surface temperatures in MGCR core after loss of coolant / Webb, G.B.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.10.28
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| 11 |
GAMD-1139
HTGR carbon transport as A function of the purification flow rate and steam inleakage / Mulvihill, R.J.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.12.15
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| 12 |
GAMD-1206
HTGR steam generator part load performance with graphite clad reactor fuel elements / Richards, N.W.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.1.21
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| 13 |
GAMD-1224
A fortran program for studying the core colling capacity of a helium-air mixture / Kaestner, R.C., Mulvihill, R.J.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.2
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| 14 |
GAMD-1229
An apparatus for measuring the thermal conductivity of graphite at high temperatures / Goeddel, W.V.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1959.1.10
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| 15 |
GAMD-1248
Progress report of some recent HTGR nuclear design studies / Bornstein, I. [et al.]
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.2.10
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| 16 |
GAMD-1251
I.B.M. 650 program for the calculation of capture-scattering and total cross-sections for S-, P- and D-wave neutrons / Crafton, C., Roos, B.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.2
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| 17 |
GAMD-1270
Methods used in MGCR nuclear survey / Stein, J.M., Vieweg, H.A.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.3
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| 18 |
GAMD-1347
Program for the estimates of resonance integrals / Crafton, C., Garrison, J.D.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.4.5
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| 19 |
GAMD-1416
Overall reactor heat transfer coefficients for transient analysis / Thompson, W.I.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.5
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| 20 |
GAMD-1439
Cell and core neutron calculations performed with the one-dimensional transport code, DSN, with reference to the HTGR critical assembly / Fenech, H., Wikner, N.F.
San Diego, CA (USA) : General Atomics Div., General Dynamics Corp. , 1960.6.8
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| 21 |
GAMD-1610
MGCR hot helium recirculating ball screw tests / Liederbach, F., Hawke, B.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.8.17
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| 22 |
GAMD-1619
The (n,2n) effect in a BeO moderator / Goodjohn, A.J., Hinman, G.W.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.8.23
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| 23 |
GAMD-1700
Report to reactor safeguards committee on the MGCR-4 fuel irradiation capsule / Johnson, D.E.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.9.21
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| 24 |
GAMD-1751
Pressure: Temperature and relief valve considerations for the HTGR reactor pressure vessel / Kalk, W., Kantor, M.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.11.8
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| 25 |
GAMD-1769
STABILITY AND PROPERTIES OF ALLOY STEELS AT ELEVATED TEMPERATURES; A LITERATURE SURVEY. / SIMNAD, M.T.
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| 26 |
GAMD-1769
The stability and properties of alloy steels at elevated temperatures. A literature survey / Simnad, M.T.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1960.11.21
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| 27 |
GAMD-1892
Temperature distribution and thermal stresses in a slab with exponental heat source / Menzel, H.F.
San Diego, CA (USA) : General Atomic Div., General Dynamics Crop. , 1961.1.5
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| 28 |
GAMD-1950
Nuclear properties for fission products of radiological significance in HTGR / Leon, H.I., Morse, D.C.
San Diego, CA (USA) : General Atomics Div., General Dynamics Corp. , 1961.1.16
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| 29 |
GAMD-2071
A coolant monitoring system for HTGR / Dunning, T.G.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1961.2.28
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| 30 |
GAMD-2079
Recent progress in HTGR internal fission product trapping studies / Watkins, R.M.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1961.2.24
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| 31 |
GAMD-2124
Definition of instantaneous conversion ratio and its variation during the first 200 days of the 40 eMW'S life / Jaye, S., Wikner, N.F.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1961.3.23
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| 32 |
GAMD-2251
Construction of Hanford test element, MGCR-HDR-3 / Wyman, W.L.
San Diego, CA (USA) : General Atomic Div. General Dynamics Corp. , 1961.5.11
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| 33 |
GAMD-2309
Ebor core element temperatures following a loss-of-coolant accident / Katz, R.
San Diego, CA (USA) : General Atomic , 1961.6
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| 34 |
GAMD-2605(REV.2)
PRIMARY COOLANT SYSTEM BLOWDOWN ACCIDENT FOR PEACH BOTTOM HTGR. / LANDONI, J.A.(et al.)
, 1962
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| 35 |
GAMD-2887
Fortran ectoplasm program / Naliboff, Y.D.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1962.1.25
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| 36 |
GAMD-2906
Milne problem for a multiplying system / Parks, D.E.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1962.1.31
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| 37 |
GAMD-3033
GATHERMOS--A new version of the thermos code / Honeck, H.C.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1962.3.21
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| 38 |
GAMD-3269
Temperature distribution in ebor fuel rods DUE to non-uniform circumferential cooling / Katz, R.
San Diego, CA (USA) : General Atomic Div. General Dynamics Corp. , 1962.6.29
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| 39 |
GAMD-3419
SHIELDING DATA FOR THE 10 MW EBOR. / SEIBOLD, J.R.(et al.)
, 1962
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| 40 |
GAMD-3611
The development and irradiation of a 19-rod-bundle fuel element / Hopkins, H.C. Jr., Kott, B.E.
San Diego, CA (USA) : General Atomic Div., General Dynamics Corp. , 1962.10.30
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| 41 |
GAMD-3877
POISON EQUIVALENT MEASUREMENT OF THE WORTH OF INDIVIDUAL HTGR CONTROL RODS WITHIN A REGION OF INFLUENCE. / SAMPSON, J.B.
, 1963
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| 42 |
GAMD-5432
THERMAL PROTECTION OF CONCRETE PRESSURE VESSEL BY LAMINATED INSULATION AND INTERNAL COOLING. / CAVALLARO, L.
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| 43 |
GAMD-6145
ADVANCED HTGR FUEL ELEMENT VIBRATION TESTS. / KIEFER, R.J.(et al.)
, 1964
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| 44 |
GAMD-6321
The release of condensable fission products from the gail III-B fuel element / Zumwalt, L.R., Busch, D.D.
San Diego, CA (USA) : General Atomic, John Jay Hopkins Lab. for Pure and Applied Science , 1965.4.19
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| 45 |
GAMD-6360
FEASIBILITY STUDY FOR REPROCESSING HTGR FUELS BASED ON USING THE NUCLEAR FUEL SERVICES, INC., REPROCESSING PLANT. / REESE, S.L.(et al.)
, 1964
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| 46 |
GAMD-7294
Design study and economic evaluation of head-end reprocessing facility integral with an HTGR power plant / Stelling, H.E., Steyer, K.G.
San Diego, CA (USA) : General Dynamics Corp., General Atomic Div. , 1968
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| 47 |
GAMD-7353
Flux distribution measurements in peach bottom: Results of post construction R and D test procedures BP-8, 10, 12 / Lane, R.K., Weiman, A.L.
San Diego, CA (USA) : General Dynamics Corp., General Atomic Div. , 1966
|
| 48 |
GAMD-7535
FREVAP-8 code for estimating the release of metallic fission products from HTGR fuel elements / Zumwalt, L.R.
San Diego, CA (USA) : General Dynamics Corp., General Atomic Div. , 1966
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| 49 |
GAMD-8119
BLOOST-6: A kinetics code containing a thermodynamic model of coated particles for HTGR applications / Dahlberg, R.C., Merrill, M.H.
San Diego, CA (USA) : General Dynamics Corp., General Atomic Div. , 1967
|
| 50 |
GAMD-8330
PROCESS STUDIES FOR LOADING BONDED BED FUEL RODS. / HOOKER, J.R.(et al.)
, 1967
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| 51 |
GAMD-8734
HTGR POWER PLANT CONTROL USING MANUAL, AUTOMATIC, AND DIGITAL COMPUTER CONTROL. / KRELL, J.(et al.)
, 1968
|
| 52 |
GAMD-9145
CENTRAL REFABRICATION PLANT FOR HTGR FUELS / Stelling, H.E.
San Diego, CA (USA) : Gulf General Atomic, Inc. , 1969
|
| 53 |
GAMD-9245
Summary compilation of Gulf General Atomic coated particle irradiation experiments / Harmon, D.P.
San Diego, CA (USA) : Gulf General Atomic, Inc., , 1968.12.30
|
| 54 |
GAMD-9280
FRICTION AND WEAR TESTS ON TOP REFLECTOR KEYED PLENUM ELEMENT MATERIALS OF THE FT. ST. VRAIN HTGR. / HEDGECOCK, P.D.
, 1969
|
| 55 |
GAMD-9478
Refabrication costs for HTGR fuels containing thorium-diluted /sup 233/U particles / Stelling, H.E.
San Diego, CA (USA) : Gulf General Atomic, Inc. , 1969
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Mendeley出力
