ABCDEFGHIJKLMNOPQRSTUVWXYZ
1
Box No.Barcode No.Report No.SuffixTitlePrint OCLC No.Electronic OCLC No.Serial InfoHT/UNT StatusHT/UNT URLComments
2
MFICHEBox005ANCR
UNT1000No. 2
Gamma-ray spectrum catalogue : Ge (Li) and Si (Li) spectrometry /
22749601125256464
http://digital.library.unt.edu/ark:/67531/metadc1535999/
3
MFICHEBox005ANCR
UNT1001
Fabrication and evaluation of samples for the irradiation portion of the fbr physics constants program /
8627356621125258930
http://digital.library.unt.edu/ark:/67531/metadc1536000/
4
MFICHEBox005ANCR
UNT1002Summary of ETR critical facility safety analysis information /2201575751125261879
http://digital.library.unt.edu/ark:/67531/metadc1536001/
5
MFICHEBox005ANCR
UNT1004Nonradioactive waste oil disposal study /9298412431125264588
http://digital.library.unt.edu/ark:/67531/metadc1536002/
6
MFICHEBox005ANCR
UNT1005Solid waste disposal methodology study /9298414401125264834
http://digital.library.unt.edu/ark:/67531/metadc1536003/
7
MFICHEBox005ANCR
UNT1006Nonradioactive waste solvent disposal study /9298413861125264835
http://digital.library.unt.edu/ark:/67531/metadc1536004/
8
MFICHEBox005ANCR
UNT1007Instrumentation and control branch annual report /1124935370
http://digital.library.unt.edu/ark:/67531/metadc1536005/
9
MFICHEBox005ANCR
UNT1008
Methods used for physics analysis of the power burst facility and computed results for the design core /
9298413871125265065
http://digital.library.unt.edu/ark:/67531/metadc1536007/
10
MFICHEBox005ANCR
UNT1009
Approximation of subcooled depressurization and core hydraulic loading in PWR vessels : an empirical method and computer application /
8629375931125265144
http://digital.library.unt.edu/ark:/67531/metadc1536008/
11
MFICHEBox005ANCR
UNT1010
Analytical method for calculating steady-state fission gas release--fission product fuel model (FPFM) code /
8629432911125264978
http://digital.library.unt.edu/ark:/67531/metadc1536009/
12
MFICHEBox005ANCR
UNT1011Pt . 1
Final safety analysis report for the power burst facility : parts I and II /
1125153910
http://digital.library.unt.edu/ark:/67531/metadc1536010/
13
MFICHEBox005ANCR
UNT1011Pt. 2.
Final safety analysis report for the power burst facility : parts I and II /
1126279364
http://digital.library.unt.edu/ark:/67531/metadc1536011/
14
MFICHEBox005ANCR
UNT1013Reactor technology branch annual report fiscal year 1970 /8629437801125265037
http://digital.library.unt.edu/ark:/67531/metadc1536014/
15
MFICHEBox005ANCR
UNT1014
Semiscale blowdown and emergency core cooling (ECC) project test report -- test 845 (ECC Injection) /
8629444631125265142
http://digital.library.unt.edu/ark:/67531/metadc1536012/
16
MFICHEBox005ANCR
UNT1015ATR extended burnup program /8628212991125265266
http://digital.library.unt.edu/ark:/67531/metadc1536013/
17
MFICHEBox005ANCR
UNT1016
Nuclear technology division annual progress report for period ending June 30, 1971.
9298414571125265366
http://digital.library.unt.edu/ark:/67531/metadc1536015/
18
MFICHEBox005ANCR
UNT1019PBF training and qualification program /9298414591125265462
http://digital.library.unt.edu/ark:/67531/metadc1536016/
19
MFICHEBox005ANCR
UNT1019(Rev. 1)Selection, training and qualification of PBF personnel /1125265471
http://digital.library.unt.edu/ark:/67531/metadc1536017/
20
MFICHEBox005ANCR
UNT1022RAFFLE general purpose Monte Carlo code /1125265533
http://digital.library.unt.edu/ark:/67531/metadc1536018/
21
MFICHEBox005ANCR
UNT1024Evaluation of failure and failure related data /9298414601125265616
http://digital.library.unt.edu/ark:/67531/metadc1536019/
22
MFICHEBox005ANCR
UNT1026
Astem- a collection of fortran subroutines to evaluate the 1967 ASME equations of state for water/steam and derivatives of these equations /
9298414691125265725
http://digital.library.unt.edu/ark:/67531/metadc1536020/
23
MFICHEBox005ANCR
UNT1027
Performance evaluation of core II and III advanced test reactor fuel elements /
8628198661125265665
http://digital.library.unt.edu/ark:/67531/metadc1536021/
24
MFICHEBox005ANCR
UNT1032
Phase I topical report. Flowing gas, non-nuclear experiments on the gas core reactor /
9298413881125265670
http://digital.library.unt.edu/ark:/67531/metadc1536022/
25
MFICHEBox005ANCR
UNT1033
Corrosion of thermocouple sheath materials in a pressurized water reactor environment /
8628193841125265640
http://digital.library.unt.edu/ark:/67531/metadc1536023/
26
MFICHEBox005ANCR
UNT1035
INSPECT: an interactive computer code for unfolding neutron spectra from activation measurements.
9212131461125265744
http://digital.library.unt.edu/ark:/67531/metadc1536024/
27
MFICHEBox005ANCR
UNT1036
Semiscale blowdown and emergency core cooling (ECC) project test report -- Tests 848, 849, and 850 (ECC Injection) /
8628190661125265792
http://digital.library.unt.edu/ark:/67531/metadc1536025/
28
MFICHEBox005ANCR
UNT1037
Transient response of transducers definitions and characteristics /
9298414491125265839
http://digital.library.unt.edu/ark:/67531/metadc1536026/
29
MFICHEBox005ANCR
UNT1038
Evaluation of filament-type electric heater rods as employed in single-loop semiscale to simulate UO₂ fuel rods /
8628147911125265862
http://digital.library.unt.edu/ark:/67531/metadc1536027/
30
MFICHEBox005ANCR
UNT1039
FP9 floating point arithmetic software for DEC PDP-9 and PDP-15 computers /
9298414501125265821
http://digital.library.unt.edu/ark:/67531/metadc1536028/
31
MFICHEBox005ANCR
UNT1040
FP8 : floating point arithmetic software for dec PDP-8 series computers /
1125265941
http://digital.library.unt.edu/ark:/67531/metadc1536029/
32
MFICHEBox005ANCR
UNT1042Automated cross section analysis program (ACSAP) /1125266408
http://digital.library.unt.edu/ark:/67531/metadc1536030
33
MFICHEBox005ANCR
UNT1043
Gauss V : a computer program for the analysis of gamma-ray spectra from Ge (Li) spectrometers /
9298412681125266551
http://digital.library.unt.edu/ark:/67531/metadc1536031/
34
MFICHEBox005ANCR
UNT1044235 U resolved resonance parameters for ENDF/B, version III /9298414381125266437
http://digital.library.unt.edu/ark:/67531/metadc1536032/
35
MFICHEBox005ANCR
UNT1045Evaluation of the ²³⁹Pu cross sections in the resonance region for the ENDF/B version III data file /1125326159
http://digital.library.unt.edu/ark:/67531/metadc1536041/
36
MFICHEBox005ANCR
UNT1046
Conductivity-sensitive liquid level detector for reactor environment /
9298414391125270348
http://digital.library.unt.edu/ark:/67531/metadc1536033/
37
MFICHEBox005ANCR
UNT1047
Ultrasonic liquid level detector using surface wave attenuation in a tube /
9298412691125270431
http://digital.library.unt.edu/ark:/67531/metadc1536034/
38
MFICHEBox005ANCR
UNT1048
Development of B4C aluminum foils as controllable neutron absorbers in aluminum clad nuclear reactor fuel plates /
9298414961125270399
http://digital.library.unt.edu/ark:/67531/metadc1536035/
39
MFICHEBox005ANCR
UNT1049
Effect of geometry and other parameters on bottom flooding heat transfer associated with nuclear fuel bundle simulators /
8628137871125325953
http://digital.library.unt.edu/ark:/67531/metadc1536038/
40
MFICHEBox005ANCR
UNT1050Experiment description and hazards evaluation for the irradiation of FBR physics constants samples in the EBR-II /1125326072
http://digital.library.unt.edu/ark:/67531/metadc1536039/
41
MFICHEBox005ANCR
UNT1051Mona : a multigroup one-dimensional neutronics analysis code /9298414711125326069
http://digital.library.unt.edu/ark:/67531/metadc1536040/
42
MFICHEBox005ANCR
UNT1052
NRTS 360/75 computer system job accounting and scheduling routines /
9298414721125326141
http://digital.library.unt.edu/ark:/67531/metadc1536042/
43
MFICHEBox005ANCR
UNT1053
Comparison of thermal-hydraulic response of loft and a large pressurized water reactor to loca conditions /
8628125351125326925
http://digital.library.unt.edu/ark:/67531/metadc1536043/
44
MFICHEBox005ANCR
UNT1054
Viewpin : a fortran program to calculate view factors for cylindrical pins /
9298414741125327473
http://digital.library.unt.edu/ark:/67531/metadc1536044/
45
MFICHEBox005ANCR
UNT1055
Relatively simple and precise technique for the assay of plutonium waste /
9298415031125341510
http://digital.library.unt.edu/ark:/67531/metadc1536045/
46
MFICHEBox005ANCR
UNT1057
Reactor gamma heat measurements with thermoluminescent phosphors /
8628119321125341704
http://digital.library.unt.edu/ark:/67531/metadc1536046/
47
MFICHEBox005ANCR
UNT1060Total neutron cross section of 243Am from 0.5 eV 1000 eV /9298415061125342055
http://digital.library.unt.edu/ark:/67531/metadc1536047/
48
MFICHEBox005ANCR
UNT1062
In-core eddy-current measurements of the ATR fuel element channel spacing /
1125342480
http://digital.library.unt.edu/ark:/67531/metadc1536048/
49
MFICHEBox005ANCR
UNT1063Damage in highly irradiated 1100 aluminum /1125342799
http://digital.library.unt.edu/ark:/67531/metadc1536049/
50
MFICHEBox005ANCR
UNT1065Semiscale project test data report : test 851 /8628099201126279600
http://digital.library.unt.edu/ark:/67531/metadc1536050/
51
MFICHEBox005ANCR
UNT1066Self-shielding in stacked foils /8627476681126283662
http://digital.library.unt.edu/ark:/67531/metadc1536051/
52
MFICHEBox005ANCR
UNT1068
C-SURE : cross sections for unresolved resonances from ENDF/B /
1126283736
http://digital.library.unt.edu/ark:/67531/metadc1536052/
53
MFICHEBox005ANCR
UNT1069
Gamma rays emitted by the físsionable nuclides and associated isotopes /
82063261126283711
http://digital.library.unt.edu/ark:/67531/metadc1536053/
54
MFICHEBox005ANCR
UNT1071Calculated reactivity of vins /1126283705
http://digital.library.unt.edu/ark:/67531/metadc1536054/
55
MFICHEBox005ANCR
UNT1072
ATR data system operational guide volume 1 : CDC-636 computer system /
1126284358
http://digital.library.unt.edu/ark:/67531/metadc1536055/
56
MFICHEBox005ANCR
UNT1074Instrumentation and control branch annual report /1124935370
http://digital.library.unt.edu/ark:/67531/metadc1536006/
57
MFICHEBox005ANCR
UNT1075PBF administrative control of construction component tests /1126334191
http://digital.library.unt.edu/ark:/67531/metadc1536056/
58
MFICHEBox005ANCR
UNT1076PBF system operation test : operations phase plan /1126333917
http://digital.library.unt.edu/ark:/67531/metadc1536057/
59
MFICHEBox005ANCR
UNT1077Gamma heating in reflector heat shield of gas core reactor /1126334804
http://digital.library.unt.edu/ark:/67531/metadc1536058/
60
MFICHEBox005ANCR
UNT1078Comparison of the fatigue and creep-fatigue properties of the unirradiated and irradiated type 304 and 316 stainless steel at 593°C (1100°F) /1126335146
http://digital.library.unt.edu/ark:/67531/metadc1536059/
61
MFICHEBox005ANCR
UNT1080
Reactor physics results from the ATR power demonstration program /
1126336311
http://digital.library.unt.edu/ark:/67531/metadc1536060/
62
MFICHEBox005ANCR
UNT1081
Evaluation (using a hybrid computer) of a sheath type electrical heater rod for simulating the response of a nuclear fuel rod /
8627447321066006566
http://digital.library.unt.edu/ark:/67531/metadc1536061/
63
MFICHEBox005ANCR
UNT1082ATRC safety analysis report : supplement-1 of IDO-16950-1 /8627449941065899325
http://digital.library.unt.edu/ark:/67531/metadc1536062/
64
MFICHEBox005ANCR
UNT1083DWARF : a few group, one-dimensional, diffusion theory program for reactor depletion with adjustable reactivity feedback /1066023817
http://digital.library.unt.edu/ark:/67531/metadc1536063/
65
MFICHEBox005ANCR
UNT1084Evaluation of ETR stability via rod drop effects /1065716727
http://digital.library.unt.edu/ark:/67531/metadc1536064/
66
MFICHEBox005ANCR
UNT1085ETR power : variation analysis /8627469091065939216
http://digital.library.unt.edu/ark:/67531/metadc1536065/
67
MFICHEBox005ANCR
UNT1086Technique for assay of L-10 bottles of plutonium nitrate : II. additional measurements and considerations /873856106
http://digital.library.unt.edu/ark:/67531/metadc1536066/
68
MFICHEBox005ANCR
UNT1087Metallurgical evaluation of welding and heat treating procedures for the inconel 718 PBF in-pile tube /1065995976
http://digital.library.unt.edu/ark:/67531/metadc1536067/
69
MFICHEBox005ANCR
UNT1088Nuclear Technology Division annual progress report for period ending June 30, 1972 /953397737
http://digital.library.unt.edu/ark:/67531/metadc1536068/
70
MFICHEBox005ANCR
UNT1089
Annual report of the Nuclear Safety Development branch, January 1--December 31, 1970 /
145567361065960215
http://digital.library.unt.edu/ark:/67531/metadc1536069/
71
MFICHEBox005ANCR
UNT1093
PBF type reactor as a driver for fission-stimulated laser experiments /
1065878776
http://digital.library.unt.edu/ark:/67531/metadc1536070/
72
MFICHEBox005ANCR
UNT1095Detailed test plan report for PBF Test Series PCM-20 : the behavior of unirradiated PWR fuel rods under power-cooling-mismatch conditions /1065882682
http://digital.library.unt.edu/ark:/67531/metadc1536071/
73
MFICHEBox005ANCR
UNT1096Fatigue and creep-fatigue behavior of irradiated stainless steels : available data, simple correlations, and recommendations for additional work in support of LMFBR design /1065911474
http://digital.library.unt.edu/ark:/67531/metadc1536072/
74
MFICHEBox005ANCR
UNT1097Heat-to-heat variations in the fatigue and creep-fatigue behavior of AISI type 304 stainless steel, and the fatigue behavior of type 308 stainless steel weld material /1065656436
http://digital.library.unt.edu/ark:/67531/metadc1536073/
75
MFICHEBox005ANCR
UNT1098
Synthetic tree model : a formal methodology for fault tree construction /
9760116681065629667
http://digital.library.unt.edu/ark:/67531/metadc1536074/
76
MFICHEBox005ANCR
UNT1099NRTS OS/360 CALCOMP plot writer /1065899320
http://digital.library.unt.edu/ark:/67531/metadc1536075/
77
MFICHEBox005ANCR
UNT1100
Protective shipping packages for radioactive and fissile material containers /
1065623891
http://digital.library.unt.edu/ark:/67531/metadc1536076/
78
MFICHEBox005ANCR
UNT1101Test and analysis of TRA seismic scram switches /1065876902
http://digital.library.unt.edu/ark:/67531/metadc1536077/
79
MFICHEBox005ANCR
UNT1103RALPH : an online computer program for acquisition and reduction of pulse height data /1065668392
http://digital.library.unt.edu/ark:/67531/metadc1536078/
80
AECBox144390150952793551105
Telemetered profiling isotopic snow gauge : final report and specifications /
36175703
NOT ON HT 01/11/2023
https://babel.hathitrust.org/cgi/pt?id=mdp.39015095279355
81
MFICHEBox005ANCR
UNT1107Computer predicted outer shim positions for criticality in the advanced test reactor /953397528
http://digital.library.unt.edu/ark:/67531/metadc1536079/
82
MFICHEBox005ANCR
UNT1115Boiling water reactor-full length emergency core cooling heat transfer (BWR- FLECHT) tests project : final report on atmospheric pressure stainless steel experiments /953397446
http://digital.library.unt.edu/ark:/67531/metadc1536080/
83
MFICHEBox005ANCR
UNT1116
Performance measurements on the NRTS IBM 360/75 computer system /
1065992703
http://digital.library.unt.edu/ark:/67531/metadc1536081/
84
MFICHEBox005ANCR
UNT1118Flowing gas, non-nuclear experiments on the gas core reactor : phase II topical report /1129589710
http://digital.library.unt.edu/ark:/67531/metadc1536082/
85
MFICHEBox005ANCR
UNT1119IBM 360/FR-80 online computer output microfilm system /953397502
http://digital.library.unt.edu/ark:/67531/metadc1536083/
86
MFICHEBox005ANCR
UNT1120Feasibility study of full-reactor gas core demonstration test /1129591037
http://digital.library.unt.edu/ark:/67531/metadc1536084/
87
MFICHEBox005ANCR
UNT1121Shrinkage evaluation in mechanized welded 16-inch-diameter circumferential pipe joints /1129591188
http://digital.library.unt.edu/ark:/67531/metadc1536085/
88
MFICHEBox005ANCR
UNT1124
Theoretical basis for calculating diffusion of fission products in fuel pins /
1129591219
http://digital.library.unt.edu/ark:/67531/metadc1536086/
89
MFICHEBox005ANCR
UNT1125Strain fatigue and tensile behavior of Inconel 718 from room temperature to 650[degrees]C /953397531
http://digital.library.unt.edu/ark:/67531/metadc1536087/
90
MFICHEBox005ANCR
UNT1126Short- and long-range potential functions for valence-bonded crystals using valence symmetry coordinates /1130233687
http://digital.library.unt.edu/ark:/67531/metadc1536088/
91
MFICHEBox005ANCR
UNT1127Rev.
RELAP4: a computer program for transient thermal hydraulic analysis /
1125270484
http://digital.library.unt.edu/ark:/67531/metadc1536036/
92
MFICHEBox005ANCR
UNT1127
RELAP4: a computer program for transient thermal hydraulic analysis /
1130234112
http://digital.library.unt.edu/ark:/67531/metadc1536089/
93
MFICHEBox005ANCR
UNT1129Nuclear Technology Division annual progress report for period ending June 30, 1973 /1066559074
http://digital.library.unt.edu/ark:/67531/metadc1536090/
94
MFICHEBox005ANCR
UNT1130Variable reluctance displacement transducer temperature compensated to 650[degrees]F /1066358985
http://digital.library.unt.edu/ark:/67531/metadc1536091/
95
MFICHEBox005ANCR
UNT1133X-RAY : an on-line program for automatic electron microanalysis of oxides and silicates using a Si(Li) spectrometer /1130236339
http://digital.library.unt.edu/ark:/67531/metadc1536092/
96
MFICHEBox005ANCR
UNT1134Fission fragment driven (d+t) neutron irradiation source for CTR materials damage irradiations /1130238157
http://digital.library.unt.edu/ark:/67531/metadc1536093/
97
MFICHEBox005ANCR
UNT1135Analysis of V, Cr, and Mn in carbon and low-alloy steel by x-ray fluorescence with an Ni-59 source /1130240653
http://digital.library.unt.edu/ark:/67531/metadc1536094/
98
MFICHEBox005ANCR
UNT1137Facility operating manual : low power test facility /1130264734
http://digital.library.unt.edu/ark:/67531/metadc1536095/
99
MFICHEBox005ANCR
UNT1138Low temperature demonstration geothermal power plant in the Raft River Valley /1130287742
http://digital.library.unt.edu/ark:/67531/metadc1536096/
100
MFICHEBox005ANCR
UNT1139FY 1974 program plan for geothermal project /1130288273
http://digital.library.unt.edu/ark:/67531/metadc1536097/