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  • 1
    Online Resource
    Online Resource
    Nuclear Fission and Neutron-Induced Fission Cross-Sections : A Nuclear Energy Agency Nuclear Data Committee (OECD) Series: Neutron Physics and Nuclear Data in Science and Technology. (1981)
    San Diego :Elsevier Science & Technology,
    Details
    Keywords: Nuclear fission. ; Electronic books.
    Type of Medium: Online Resource
    Pages: 1 online resource (294 pages)
    Edition: 1st ed.
    ISBN: 9781483189765
    URL: https://ebookcentral.proquest.com/lib/geomar/detail.action?docID=1834388
    Language: English
    Note: Font Cover -- Nuclear Fission and Neutron-Induced Fission Cross-Sections -- Copyright Page -- Table of Contents -- PREFACE -- LIST OF ABBREVIATIONS -- Chapter I. INTRODUCTION -- Chapter II. BASIC PHYSICS OF THE FISSION PROCESS -- II. A INTRODUCTION -- II. B VARIOUS PHASES OF THE FISSION PROCESS -- II.C SOME PROPERTIES OF THE LOW-ENERGY FISSION OF ACTINIDE NUCLEI -- II.D NEUTRON-INDUCED FISSION -- Chapter III. FISSION CROSS-SECTION REQUIREMENTS FOR THE NUCLEAR ENERGY PROGRAMME -- III.A INTRODUCTION -- III.B FUEL CYCLES AND THE QUALITATIVE ROLE OF NUCLEAR DATA -- III.C REACTOR CALCULATIONS AND THE QUANTITATIVE ROLE OF NUCLEAR DATA -- III.D INTEGRAL MEASUREMENTS -- III.E SUMMARY OF FISSION CROSS-SECTION REQUIREMENTS FOR THE NUCLEAR ENERGY PROGRAMME -- Chapter IV. MEASUREMENTS OF FISSION CROSS-SECTIONS -- IV.A INTRODUCTION -- IV.B ESSENTIALS OF CROSS-SECTION MEASUREMENTS -- IV.C MEASUREMENT TECHNIQUES -- IV.D FISSION DETECTION -- IV.E SELECTED EXAMPLES OF FISSION CROSS-SECTION MEASUREMENTS -- IV.F DATA REDUCTION AND STORAGE -- IV.G DATA ANALYSIS -- IV.H DATA EVALUATION -- IV.I COMPARISON OF EXPERIMENTAL RESULTS WITH NEEDS -- IV.J FUTURE MEASUREMENTS -- Chapter V. THEORETICAL METHODS FOR CALCULATING THE CROSS-SECTIONS OF FISSIONABLE NUCLEI -- V.A INTRODUCTION -- V.B THE COMPOUND NUCLEUS AND HAUSER-FESHBACH THEORY -- V.C CALCULATION OF NEUTRON TRANSMISSION COEFFICIENTS -- V.D RADIATIVE TRANSMISSION COEFFICIENTS -- V.E LEVEL DENSITIES -- V.F FISSION TRANSMISSION COEFFICIENTS -- V.G COMPUTATIONAL METHODS FOR CALCULATING CROSS-SECTIONS OF FISSIONABLE NUCLIDES -- V.H CONCLUSIONS -- Chapter VI. CONCLUSION -- REFERENCES -- GLOSSARY -- SUBJECT INDEX.
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  • 2
    Online Resource
    Online Resource
    Neutron Capture Gamma-Ray Spectroscopy. (1979)
    New York, NY :Springer,
    Details
    Keywords: Neutron capture gamma ray spectroscopy-Congresses. ; Electronic books.
    Type of Medium: Online Resource
    Pages: 1 online resource (875 pages)
    Edition: 1st ed.
    ISBN: 9781461329404
    URL: https://ebookcentral.proquest.com/lib/geomar/detail.action?docID=6705771
    Language: English
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  • 3
    Online Resource
    Online Resource
    Neutron Radiative Capture : Neutron Physics and Nuclear Data in Science and Technology. (1984)
    San Diego :Elsevier Science & Technology,
    Details
    Keywords: Neutrons -- Capture. ; Electronic books.
    Type of Medium: Online Resource
    Pages: 1 online resource (285 pages)
    Edition: 1st ed.
    ISBN: 9781483152431
    URL: https://ebookcentral.proquest.com/lib/geomar/detail.action?docID=1834300
    Language: English
    Note: Front Cover -- Neutron Radiative Capture -- Copyright Page -- Table of Contents -- Preface -- LIST OF ABBREVIATIONS -- INTRODUCTION -- Chapter I. THEORY OF SLOW NEUTRON RADIATIVE CAPTURE -- I.A INTRODUCTION -- I.B STATISTICAL THEORY OF RADIATIVE CAPTURE -- I.C SYSTEMATIC PROPERTIES OF RADIATIVE NEUTRON CAPTURE -- Chapter II. FAST NEUTRON RADIATIVE CAPTURE -- II.A DIRECT AND SEMIDIRECT CAPTURE REACTIONS -- II.B EXPERIMENTAL RESULTS -- Chapter III. METHODS FOR CALCULATING NEUTRON CAPTURE CROSS SECTIONS AND GAMMA-RAY ENERGY SPECTRA -- III.A SCOPE -- III.B STATISTICAL MODEL CALCULATIONS -- III.C EXPRESSIONS FOR E1 PHOTON STRENGTHS -- III.D GIANT DIPOLE RESONANCE SYSTEMATICS -- III.E NUCLEAR LEVEL DENSITIES -- III.F SAMPLE CALCULATION: 89Υ(n,γ)90Υ -- III.G SUMMARY -- Chapter IV. MEASUREMENT TECHNIQUES FOR RADIATIVE NEUTRON CAPTURE -- IV.A INTRODUCTION -- IV.B CAPTURE EVENT DETECTION -- IV.C ANALYSIS OF MEASUREMENTS -- Chapter V. NEUTRON CAPTURE PROCESSES IN FISSION REACTORS -- V.A INTRODUCTION -- V.B CAPTURE IN FERTILE AND FISSILE NUCLEI -- V.C CAPTURE IN STRUCTURAL, COOLANT AND SHIELDING MATERIALS -- V.D CAPTURE IN FISSION PRODUCT NUCLEI -- V.E THE PRODUCTION OF HIGHER ACTINIDES -- Chapter VI. APPLICATIONS TO STELLAR NUCLEOSYNTHESIS -- VI.A INTRODUCTION -- VI.B s-Process Nucleosynthesis -- VI.C AGE OF THE s-PROCESS AND THE STELLAR ENVIRONMENT -- VI.D r-PROCESS CHRONOMETER AND THE AGE OF THE UNIVERSE -- VI.E SUMMARY -- Chapter VII. PRACTICAL USES OF NEUTRON CAPTURE GAMMA-RAY SPECTROSCOPY -- VII.A INTRODUCTION -- VII.B FUNDAMENTALS -- VII.C THE PROMPT GAMMA-RAY TECHNIQUE (PGA) -- VII.D NON-ANALYTICAL USES OF NEUTRON CAPTURE -- VII.E CONCLUSIONS -- ACKNOWLEDGEMENTS -- Chapter VIII. SUMMARY AND CONCLUDING REMARKS -- REFERENCES -- GLOSSARY -- SUBJECT INDEX.
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  • 4
    Electronic Resource
    Electronic Resource
    Fusion neutrons from the gas–pusher interface in deuterated-shell inertial confinement fusion implosions (1998)
    [S.l.] : American Institute of Physics (AIP)
    Physics of Plasmas 5 (1998), S. 768-774 
    Details
    ISSN: 1089-7674
    Source: AIP Digital Archive
    Topics: Physics
    Notes: The first measurements and numerical simulations of fusion neutrons from the gas–pusher interface of indirectly-driven inertial confinement fusion implosions have been performed using hydrogen-filled capsules made with a deuterated inner layer. Nonlinear saturation of the growth of hydrodynamic perturbations in high linear growth factor ((similar, equals)325) implosions was varied by adjusting the initial surface roughness of the capsule. The neutron yields are in quantitative agreement with the direct simulations of perturbation growth, and also with a linear mode superposition and saturation model including enhanced thermal loss in the mixed region. Neutron spectra from these capsules are broader than expected for the calculated ion temperatures, suggesting the presence of nonthermal broadening from mass motion during the fusion burn. © 1998 American Institute of Physics.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1063/1.872761
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  • 5
    Electronic Resource
    Electronic Resource
    Neutron calibration for the FRX-C/LSM magnetic compression experiment (1991)
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 62 (1991), S. 1489-1493 
    Details
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: Neutron source strength and yield from field-reversed configurations have been measured in the FRX-C/LSM magnetic compression experiment using plastic scintillators, indium activation samples, and moderated rhodium activation counters. The calibration of these neutron detectors is complicated by the changing shape and position of the plasma and by the presence of the massive aluminum compression coils. The overall uncertainty in the neutron measurements is estimated to be 45%.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1063/1.1142473
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  • 6
    Electronic Resource
    Electronic Resource
    Moderate-convergence inertial confinement fusion implosions in tetrahedral hohlraums at Omega (2000)
    [S.l.] : American Institute of Physics (AIP)
    Physics of Plasmas 7 (2000), S. 2594-2603 
    Details
    ISSN: 1089-7674
    Source: AIP Digital Archive
    Topics: Physics
    Notes: A highly uniform thermal x-radiation field for indirect-drive inertial confinement fusion implosions may be obtained by irradiating a four-hole, tetrahedral geometry, spherical hohlraum with all 60 Omega laser beams. Implosion studies and calculations [J. M. Wallace et al., Phys. Rev. Lett. 82, 3807 (1999)] indicate a drive uniformity comparable to that expected for the National Ignition Facility [J. A. Painser et al., Laser Focus World 30, 75 (1994)]. With 60 beams distributed over the cavity wall, tetrahedral hohlraums have a natural insensitivity to power balance and pointing errors. Standard, smooth Nova capsules imploded with this drive indicate that moderate convergence-ratio implosions, Cr∼18, have measured-neutron yield to calculated-clean-one-dimensional-neutronyield ratios similar to those previously investigated using the comparatively poor drive uniformity of Nova cylindrical hohlraums. This may indicate that a nonsymmetry-related neutron yield degradation mechanism, e.g., hydrodynamic mixing of cold, dense ablator material with the hot-spot region or some combination of nonsymmetry effects, is dominating in this Cr regime. © 2000 American Institute of Physics.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1063/1.874101
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  • 7
    Electronic Resource
    Electronic Resource
    Foam-buffered spherical implosions at 527 nm (1997)
    [S.l.] : American Institute of Physics (AIP)
    Physics of Plasmas 4 (1997), S. 1379-1384 
    Details
    ISSN: 1089-7674
    Source: AIP Digital Archive
    Topics: Physics
    Notes: Creation of a low density, high temperature plasma buffer between the absorption and ablation layers of a directly driven inertial confinement fusion implosion capsule has been proposed as a means to reduce "early time" imprint from laser nonuniformities. This thermal smoothing blanket might be created from a low density foam layer wrapped around the deuterium–tritium filled microballoon. Preliminary spherical implosion tests of this concept using a polystyrene foam layer surrounding a glass microballoon were performed at the Nova laser [Rev. Sci. Instrum. 57, 2101 (1986)], using a 527 nm drive wavelength. Comparison of capsule yield and imploded core symmetry showed promising improvements in overall target performance, relative to one-dimensional undegraded hydrodynamic simulations, when the foam-buffer layer was present. © 1997 American Institute of Physics.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1063/1.872568
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  • 8
    Electronic Resource
    Electronic Resource
    Nuclear diagnostics for the National Ignition Facility (invited) : Papers from the thirteenth topical conference on high temperature plasma diagnostics (2001)
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 72 (2001), S. 773-779 
    Details
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: The National Ignition Facility (NIF), currently under construction at the Lawrence Livermore National Laboratory, will provide unprecedented opportunities for the use of nuclear diagnostics in inertial confinement fusion experiments. The completed facility will provide 2 MJ of laser energy for driving targets, compared to the approximately 40 kJ that was available on Nova and the approximately 30 kJ available on Omega. Ignited NIF targets are anticipated to produce up to 1019 DT neutrons. In addition to a basic set of nuclear diagnostics based on previous experience, these higher NIF yields are expected to allow innovative nuclear diagnostic techniques to be utilized, such as neutron imaging, recoil proton techniques, and gamma-ray-based reaction history measurements. © 2001 American Institute of Physics.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1063/1.1319356
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  • 9
    Electronic Resource
    Electronic Resource
    A sensitive neutron spectrometer for the National Ignition Facility : Papers from the thirteenth topical conference on high temperature plasma diagnostics (2001)
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 72 (2001), S. 846-849 
    Details
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: We are developing a sensitive neutron spectrometer for the National Ignition Facility laser at Livermore. The spectrometer will consist of a 1020 channel single-neutron-interaction time-of-flight detector array fielded 23 m from the neutron-producing target. It will use an existing detector array together with upgraded electronics for improved time resolution. Measurements of neutron yield, ion and electron temperatures, and density-radius product are all possible under certain conditions using one-, two-, or three-step reaction processes. The locations of the most important potential sources of scattered neutron backgrounds are determined as the first step in designing collimation to reduce these backgrounds. © 2001 American Institute of Physics.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1063/1.1323242
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  • 10
    Electronic Resource
    Electronic Resource
    Interpretation of neutron time-of-flight signals from current-mode detectors : Proceedings of the eleventh topical conference on high temperature plasma diagnostics (1997)
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 68 (1997), S. 610-613 
    Details
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: Neutron time-of-flight (nToF) signals from current-mode neutron detectors are often used to determine burn-averaged ion temperature from ICF targets because the spread of the neutron energy distribution is a function of the temperature of the reacting ions. The measured signal will, however, be a convolution of the actual neutron signal, the detector response, and the response of the recording system. In addition, scattered neutrons will arrive at the detector later than unscattered neutrons, further broadening the signal. The ion temperature derived from nToF data depends strongly on the functions used to fit the data or the methods utilized to unfold the neutron energy spectrum. A functional form based on known and measured properties of the detectors is used to fit the integral of the time-of-flight signal, allowing ion temperature derivations from targets with lower neutron yield than previously possible.
    Type of Medium: Electronic Resource
    URL: http://dx.doi.org/10.1063/1.1147763
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