Prompt neutron lifetime from time dependent thermal diffusion equation

Prompt neutron lifetime from time dependent thermal diffusion equation

Bibliographic Details
Main Author:	Hlaing, Shwe, 1936-
Language:	en_US
Published:	The University of Arizona. 1962
Subjects:	Neutrons. Nuclear reactors.
Online Access:	http://hdl.handle.net/10150/319409

Similar Items

Variational methods applied to nuclear reactor space-time neutronics
by: Favorite, Jeffrey Alan
Published: (2007)

An analytic nodal method for solving the two-group, multidimensional, static and transient neutron diffusion equations
by: Smith, Kord Sterling
Published: (2005)

Time-dependent continuous-energy solutions in neutron transport theory for plane and spherical infinite media
by: Roybal, Jerry Anthony
Published: (1981)

The determination of effective delayed neutron and photoneutron kinetics parameters in a highly enriched heavy-water reactor
by: Graham, Walter Waverly
Published: (2007)

The determination of effective delayed neutron and photoneutron kinetics parameters in a highly enriched heavy-water reactor
by: Graham, Walter Waverly
Published: (2009)

Energy correlations of prompt neutrons from 252Cf fission
by: Whittal, David Mark
Published: (2016)

Resonance region neutronics of unit cells in fast and thermal reactors.
by: Salehi, Ali Akbar
Published: (2005)

Experimental and mathematical simulation techniques for determining an in-situ response testing method for neutron sensors used in reactor power plant protection systems /
by: Behbahani, Alireza
Published: (1983)

An investigation of methods for neutron cross section error identification utilizing integral data
by: Chow, Edward Tze Yuen
Published: (2007)

Integration methods for the time dependent neutron diffusion equation and other approximations of the neutron transport equation
by: Carreño Sánchez, Amanda María
Published: (2020)

A coincidence technique for the nondestructive measurement of the neutron capture rate of a ²³⁶U foil in a zero power fast reactor /
by: Hall, Ronald James
Published: (1967)

Space- and energy-dependent noise analysis using modal expansions
by: Ebert, David Dean
Published: (2007)

4H-SiC Schottky Barrier Diodes for Efficient Thermal Neutron Detection
by: Robert Bernat, et al.
Published: (2021-09-01)

Nonlinear methods for solving the diffusion equation.
by: Shober, Robert Anthony
Published: (2005)

Determination of the neutron flux in the reactor zones with the strong neutron absorption and leakage
by: Ljubenov Vladan, et al.
Published: (2004-01-01)

Neutron transport in a complex geometry and materials arrangement
Published: (2015)

Simulated boiling effects in a subcritical assembly
by: Lord, Robert John
Published: (2006)

Design and construction of a fast neutron irradiation facility for use at elevated temperature
by: Ismuntoyo, Robertus
Published: (2011)

Variational estimates of point kinetics parameters
by: Favorite, Jeffrey Alan
Published: (2007)

Contributions to solve the Multi-group Neutron Transport equation with different Angular Approaches
by: Morato Rafet, Sergio
Published: (2021)

X-10 reactor forensic analysis and evaluation using a suite of neutron transport codes
by: Redd, Evan M.
Published: (2015)

Investigation on the Measuring Technique of the In-Core Neutron Spectra at Reactors
by: WANG Gu-jun
Published: (2017-08-01)

Influence of neutron energy on formation of radioisotopes during the irradiation of targets in reactor
by: P. M. Vorona, et al.
Published: (2011-09-01)

Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and fluent
by: Królikowski Igor P., et al.
Published: (2015-09-01)

Creation of a whole-core PWR benchmark for the analysis and validation of neutronics codes
by: Hon, Ryan Paul
Published: (2013)

Calculational investigations and analysis of characteristics of research reactor WWR-M as a source of neutrons for solution of scientific and applied tasks
by: P. M. Vorona, et al.
Published: (2010-03-01)

On the spectrum of moderated neutrons emitted by the isotropic source in the gas fuel
by: V. O. Tarasov, et al.
Published: (2016-12-01)

A coarse-mesh nodal diffusion method based on response matrix considerations.
by: Sims, Randal Nee
Published: (2005)

Design, Construction and Characterization of an External Neutron Beam Facility at The Ohio State University Nuclear Reactor Laboratory
by: Turkoglu, Danyal J.
Published: (2011)

Thermal neutron lifetime in water-reflected single spherical cavities
by: Al-Saji, Abdul Wahid R.
Published: (1969)

Numerical techniques for coupled neutronic/thermal hydraulic nuclear reactor calculations
by: Betts, Curt M.
Published: (2013)

Peaking factors in the University of Arizona research factor: core configuration, TEST-1
by: Bernat, Steven Nicholas, et al.
Published: (1981)

Experimental and theoretical investigation of the diffusion length of thermal neutrons in graphite
by: Kaiser, Richard Edward.
Published: (2015)

Neutronics Studies on the NIST Reactor Using the GA LEU fuel
by: Britton, Kyle A
Published: (2018)

Measurements of the Neutron Lifetime
by: F. E. Wietfeldt
Published: (2018-12-01)

Traveling Wave Reactor and Condition of Existence of Nuclear Burning Soliton-Like Wave in Neutron-Multiplying Media
by: Sergey I. Saulenko, et al.
Published: (2011-09-01)

PROMPT FISSION NEUTRON ENERGY SPECTRUM OF n+<sup>235</sup>U
by: McGinnis, Jason M.
Published: (2019)

THERMAL NEUTRONS IN DUCTED SHIELDS
by: Channon, Frederick Robert, 1938-
Published: (1966)

Application of nodal equivalence theory to the neutronic analysis of PWRS
by: Hoxie, Christopher Lloyd
Published: (2008)

Neutronics analysis of a modified Pebble Bed Advanced High Temperature Reactor
by: Abejon Orzaez, Jorge
Published: (2009)

Cannot write session to /tmp/vufind_sessions/sess_1kpk0p18063io83cctmjq5hpre