Nuclear Cross Sections and Technology: Proceedings of a Conference, Washington, D.C., March 3-7, 1975, Volume 1;Volume 13

Roald Amundsen Schrack, Charles D. Bowman

U.S. Department of Commerce, National Bureau of Standards, 1975 - 1003 pagina's

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PROGRAM COMMITTEE	1

The Light Water Reactor IndustryNuclear Data Needs by V O Uotinen	7

Radioactive Decay Heat Analyses by R E Schenter and F Schmittroth	13

Integral Capture CrossSection Measurements in the CFRMF for LMFBR Control	20

AA 6	29

BA 1	39

CROSS SECTIONS AND FLUX STANDARDS	42

After PHENIX What Is the Importance of Nuclear Data Programs for Fast	51

FUSION	221

A Consistent Set of Transplutonium Multigroup Cross Sections by R	224

Parameters of the Subthreshold Fission Structure in 240pu by G	231

Measurements of the 6Li and 10B Partial Cross Sections from 1 to 1500	232

Elastic and Inelastic Differential Neutron Scattering Cross Sections	238

Angular Anisotropy in the Linx3H Reaction at 25 keV by I G Schroder	240

Observation and Analysis of Elastic Neutron Scatering from 12C	246

MEASUREMENTS OF NEUTRON CROSS SECTIONS	249

INSTRUMENTS AND TECHNIQUES	62

A Thick Target Measurement Technique for Determining Nuclear Reaction	69

Excitation Curve for the Production of 115Inm by Neutron Inelastic	70

Detector Calibration with an Associated Particle Apparatus	75

Fission Cross Section Measurements on ShortLived Alpha Emitters	81

SESSION BB Continued Page	83

The 2keV Filtered Beam Facility at the NBS Reactor by I G Schroder	89

A Modular Minicomputer Multiparameter Data Gathering and Virtual Memory	97

A Facility for Studying NeutronInduced Charged Particle Reactions	103

CROSS SECTIONS AND FLUX STANDARDS	111

Facilities for Cross Section Measurements Using NaD Photoneutron Sources	112

MICROSCOPIC DATA AND TECHNIQUES	119

CROSS SECTIONS MEASUREMENTS ON FISSIONABLE	121

Data by R G Alsmiller	128

Measurement Analysis and Implications of the Fission Cross Sections	129

623	137

Neutron Capture Cross Section Measurement Techniques by R E Chrien	139

Nuclear Models and Data for GammaRay Production by P G Young	149

Cross Sections for the Production of Low Energy Photons by Neutron	155

Techniques for the Determination of Neutron Induced Charged Particle	156

The Fission Cross Section of 235U for NaBe Photoneutrons by G M Gilliam	160

Evaluation Uncertainty Estimation and Adjustment of Capture Cross Sections	165

Uncertainties and Correlations in Evaluated Data Sets Induced by Use	173

INTERNATIONAL ADVISORS TO THE PROGRAM COMMITTEE	176

SESSION CB Continued	177

Assessment of Neutron Group Constants for Iron and Stainless Steel Through	184

The Low Energy Total Cross Section of 36Ar by S F Mughabghab	190

Fission Product GammaRay and Photoneutron Spectra by M G Stamatelatos	193

The Average Number of Prompt Neutrons up from Neutron Induced Fission	195

MANAGEMENT OF THE ACTINIDES	199

Differential Elastic Scattering Cross Sections of Sulphur for 14 8	204

DA 3	209

Level and Decay Schemes of EvenA Se and Ge Isotopes from nny	210

nf Cross Sections for Exotic Actinides by J B Wilhelmy H C Britt	218

Fundamental Integral Cross Section Ratio Measurements in the ThermalNeutron	254

A Measurement of the 238235U Fission Cross Section Ratio by M S Coates	257

Manganese Bath Systematic Effects in Measurements of u and M by J R Smith	266

Measurement of Cross Sections for Threshold Reactions Induced by 252Cf	273

CROSS SECTIONS AND FLUX STANDARDS	281

642	290

572	291

Neutron Cross Section Standards and Flux Determinations Above Thermal	293

Interlaboratory Comparison of Absolute Fission Rate and 238 Capture Rate	301

Analyzing Powers of the Lint 4 He Reaction by Munawar Karim	308

EVALUATION AND CALCULATION OF CROSS SECTIONS OF NONFISSIONABLE MATERIALS	309

Spin Determination of Resonances in 235U by G A Keyworth C E Olsen	316

Description of the ENDFBIV Silicon Evaluation Energy Distributions	317

Evaluated DecayScheme Data for the ILRR Program by R G Helmer	324

Phase Shift Analysis of nD nT DD DT TT D and AT Cross Sections	326

Neutron Cross Sections and Their Uncertainties Obtained from Nuclear	332

Quantum Numbers of Low Lying Neutron Resonances in U235 by J P Felvinci	337

OddEven Fluctuations in Neutron Strength Functions by G J Kirouac	338

Theoretical Estimates of ny Cross Sections for 615 MeV Neutrons	346

SESSION EB Continued Page	354

Evaluation of the Resonance Parameters and Capture Cross Section	367

KeV Capture Cross Section of 242Pu by R W Hockenbury A J Sanislo	369

Effects of Nuclear Data Uncertainties upon LMFBR Fuel Cycle Characteristics	385

Burnup Calculations for the KWO Reactor by D C Lutz	398

GB 20	405

Analysis of the BNL Th02233U Exponential Experiments by D Dabby	415

971	417

A Comparison of AirOverGround Transport Calculations Using Different	431

SESSION FA Continued Page	444

A Comparison of VIM and MC22Two Detailed Solutions of the Neutron	451

Production Cross Sections of Some Micro and Millisecond Isomers with 14 8	456

Decay Heat Analysis for an LMFBR Fuel Assembly Using ENDFBIV Data	458

Experiments and Analysis by S Seth W Heer M Jermann	464

Overige edities - Alles bekijken

Nuclear Cross Sections and Technology: Proceedings of a ..., Volume 1;Volume 13
Roald Amundsen Schrack,Charles D. Bowman
Volledige weergave - 1975

Nuclear Cross Sections and Technology: Proceedings of a Conference ..., Volume 1
Roald A. Schrack,Charles D. Bowman
Volledige weergave - 1975

Alles bekijken »

Veelvoorkomende woorden en zinsdelen

accuracy actinides analysis average burnup calculations calibration capture cross section chamber collimator core counter cross section measurements cross-section curve decay data decay heat detector determined discrepancy distribution EBR-II effect efficiency ENDF/B ENDF/B-IV energy range energy region error estimate evaluation experimental data experiments fast reactor Figure fission cross section fission products fission rate fission spectrum fuel function gamma gamma-ray half-lives IAEA inelastic scattering integral irradiation isotopes Laboratory LMFBR method neutron capture Neutron Cross Sections neutron detector neutron energy neutron flux neutron source neutron spectrum Nucl Nuclear Cross Sections nuclear data nuclei nuclides obtained parameters particle peak photoneutron Phys plutonium present proton pulse height R-matrix radiation ratio rays reaction rates reactivity resonance s-wave sample scandium scintillator shielding shown in Fig spectra standard Table target techniques thermal thermal neutron tion total cross section uncertainty uranium values width y-ray yield

Bibliografische gegevens

Titel	Nuclear Cross Sections and Technology: Proceedings of a Conference, Washington, D.C., March 3-7, 1975, Volume 1;Volume 13 Volume 425 van NBS special publication Nuclear Cross Sections and Technology: Proceedings of a Conference, Washington, D.C., March 3-7, 1975, American Nuclear Society. Radiation Protection and Shielding Division
Redacteurs	Roald Amundsen Schrack, Charles D. Bowman
Bijdrager	American Nuclear Society. Radiation Protection and Shielding Division
Uitgever	U.S. Department of Commerce, National Bureau of Standards, 1975
Oorspronkelijk uit	Pennsylvania State University
Gedigitaliseerd	27 juni 2014
Lengte	1003 pagina's

Citatie exporteren	BiBTeX EndNote RefMan

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