Author: JF. Briesmeister
Publisher:
ISBN:
Category : Benchmark
Languages : en
Pages : 8
Book Description
Fission reaction rates for four nuclides were measured in the leakage spectrum outside spherical water moderators of various radii surrounding a 252Cf neutron source. Using the MCNP transport code, matching calculations were made with highly detailed modeling of the measurement apparatus. The calculations predicted significantly higher leakage of neutrons in the epicadmium energy range than was found in the measurements. A discrepancy of the same sign but weaker magnitude was found for thermal neutrons. These discrepancies may be relevant to problems with criticality calculations in special cases.
Neutron Leakage Benchmarks for Water Moderators
Author: JF. Briesmeister
Publisher:
ISBN:
Category : Benchmark
Languages : en
Pages : 8
Book Description
Fission reaction rates for four nuclides were measured in the leakage spectrum outside spherical water moderators of various radii surrounding a 252Cf neutron source. Using the MCNP transport code, matching calculations were made with highly detailed modeling of the measurement apparatus. The calculations predicted significantly higher leakage of neutrons in the epicadmium energy range than was found in the measurements. A discrepancy of the same sign but weaker magnitude was found for thermal neutrons. These discrepancies may be relevant to problems with criticality calculations in special cases.
Publisher:
ISBN:
Category : Benchmark
Languages : en
Pages : 8
Book Description
Fission reaction rates for four nuclides were measured in the leakage spectrum outside spherical water moderators of various radii surrounding a 252Cf neutron source. Using the MCNP transport code, matching calculations were made with highly detailed modeling of the measurement apparatus. The calculations predicted significantly higher leakage of neutrons in the epicadmium energy range than was found in the measurements. A discrepancy of the same sign but weaker magnitude was found for thermal neutrons. These discrepancies may be relevant to problems with criticality calculations in special cases.
Neutron Energy Degradation by Water Moderation
Author: Hugh F. Henry
Publisher:
ISBN:
Category : Energy dissipation
Languages : en
Pages : 66
Book Description
Publisher:
ISBN:
Category : Energy dissipation
Languages : en
Pages : 66
Book Description
Reactor Dosimetry
Author: Harry Farrar
Publisher: ASTM International
ISBN: 0803118996
Category : Nuclear reactors
Languages : en
Pages : 854
Book Description
Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa
Publisher: ASTM International
ISBN: 0803118996
Category : Nuclear reactors
Languages : en
Pages : 854
Book Description
Proceedings of the 8th ASTM-Euratom Symposium, held in Vail, Colorado, Aug.-Sept. 1993, to provide a forum for experts to discuss their latest results under the broad theme of dosimetry for the correlation of radiation effects. Preceded by a summary of the keynote presentations and followed by summa
An Investigation Using Pulsed Neutron Source Technique Into the Effect of Voids in a Water Moderator Assembly Upon Neutron Leakage
Author: Robert William Page
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
NIST Technical Note
Author:
Publisher:
ISBN:
Category : Physical instruments
Languages : en
Pages : 520
Book Description
Publisher:
ISBN:
Category : Physical instruments
Languages : en
Pages : 520
Book Description
Neutron Leakage from Hydrogen-moderated Systems
Author: Theodore Auerbach
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 24
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 24
Book Description
FENDL Neutronics Benchmark
Author: S. P. Simakov
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 16
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 16
Book Description
High Performance Light Water Reactor
Author: Thomas Schulenberg
Publisher: KIT Scientific Publishing
ISBN: 3866448171
Category : Technology & Engineering
Languages : en
Pages : 258
Book Description
Results of the project "High Performance Light Water Reactor--Phase 2," carried out September 2006-February 2010 as part of the 6th European Framework Program.
Publisher: KIT Scientific Publishing
ISBN: 3866448171
Category : Technology & Engineering
Languages : en
Pages : 258
Book Description
Results of the project "High Performance Light Water Reactor--Phase 2," carried out September 2006-February 2010 as part of the 6th European Framework Program.
LANSCE (Manuel Lujan, Jr. Neutron Scattering Center) Target System Performance
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
We measured neutron beam fluxes at LANSCE using gold foil activation techniques. We did an extensive computer simulation of the as-built LANSCE Target/Moderator/Reflector/Shield geometry. We used this mockup in a Monte Carlo calculation to predict LANSCE neutronic performance for comparison with measured results. For neutron beam fluxes at 1 eV, the ratio of measured data to calculated varies from H".6-0.9. The computed 1 eV neutron leakage at the moderator surface is 3.9 × 101° n/eV-sr-s-[mu]A for LANSCE high-intensity water moderators. The corresponding values for the LANSCE high-resolution water moderator and the liquid hydrogen moderator are 3.3 and 2.9 × 101°, respectively. LANSCE predicted moderator intensities (per proton) for a tungsten target are essentially the same as ISIS predicted moderator intensities for a depleted uranium target. The calculated LANSCE steady state unperturbed thermal (E
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
We measured neutron beam fluxes at LANSCE using gold foil activation techniques. We did an extensive computer simulation of the as-built LANSCE Target/Moderator/Reflector/Shield geometry. We used this mockup in a Monte Carlo calculation to predict LANSCE neutronic performance for comparison with measured results. For neutron beam fluxes at 1 eV, the ratio of measured data to calculated varies from H".6-0.9. The computed 1 eV neutron leakage at the moderator surface is 3.9 × 101° n/eV-sr-s-[mu]A for LANSCE high-intensity water moderators. The corresponding values for the LANSCE high-resolution water moderator and the liquid hydrogen moderator are 3.3 and 2.9 × 101°, respectively. LANSCE predicted moderator intensities (per proton) for a tungsten target are essentially the same as ISIS predicted moderator intensities for a depleted uranium target. The calculated LANSCE steady state unperturbed thermal (E
Advanced Neutron Sources 1988, Proceedings of the 10th Meeting of the INT Collaboration on Advanced Neutron Sources (ICANS X), Held at Los Alamos, October 1988
Author: International Collaboration on Advanced Neutron Sources. Meeting
Publisher: CRC Press
ISBN:
Category : Art
Languages : en
Pages : 908
Book Description
Revolving around the interaction between spectrometer and target-station design and performance, this volume emphasises the need for feedback that must exist between scientific requirements and source design. It achieves a forum for the sharing of information on the development of spallation neutron sources. Of great value to researchers in condensed matter physics, instrumentation and data processing involved in neutron scattering at pulsed and steady sources.
Publisher: CRC Press
ISBN:
Category : Art
Languages : en
Pages : 908
Book Description
Revolving around the interaction between spectrometer and target-station design and performance, this volume emphasises the need for feedback that must exist between scientific requirements and source design. It achieves a forum for the sharing of information on the development of spallation neutron sources. Of great value to researchers in condensed matter physics, instrumentation and data processing involved in neutron scattering at pulsed and steady sources.