American Nuclear Society
Home

Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 59

Volume 59

Viewing 21 to 40 of 60

Fast-Neutron Total and Scattering Cross Sections of Elemental Nickel

P. Guenther, A. Smith, J. Whalen

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 106-116

February 1976

Format:

Price:$30.00

Uncertainty Analysis of Fission-Product Decay-Heat Summation Methods

F. Schmittroth

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 117-139

February 1976

Format:

Price:$30.00

Boundary-Value Thermal-Hydraulic Analysis of a Reactor Fuel Rod Bundle

William T. Sha, Robert C. Schmitt, P. R. Huebotter

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 140-160

February 1976

Format:

Price:$30.00

A Monte Carlo Code for the Evaluation of the Thermal Design of a Nuclear Reactor Core

Kazuyoshi Miki, Kotaro Inoue

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 161-169

February 1976

Format:

Price:$30.00

Generalized Padé and Chebyshev Approximations for Point Kinetics

J. P. Hennart, B. Torres Barrios

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 170-187

February 1976

Format:

Price:$30.00

Sensitivity Theory from a Differential Viewpoint

E. M. Oblow

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 187-189

February 1976

Format:

Price:$30.00

Cross-Section Sensitivity of the D-T Fusion Probability and the D-T and T-T Reaction Rates

R. T. Santoro, J. Barish

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 189-194

February 1976

Format:

Price:$30.00

Neutron Slowing Down with Energy-Dependent Anisotropy of Scattering

D. Stefanović

Nuclear Science and Engineering / Volume 59 / Number 2 / Pages 194-198

February 1976

Format:

Price:$30.00

Methods for Detailed Thermal and Hydraulic Analysis of Water-Cooled Reactors

Joel Weisman, Robert W. Bowring

Nuclear Science and Engineering / Volume 59 / Number 2 / Page 199

February 1976

Estimation and Optimal Feedback Control Theory Applied to a Nuclear Boiling Water Reactor

B. Frogner, L. M. Grossman

Nuclear Science and Engineering / Volume 59 / Number 2 / Page 199

February 1976

Monte Carlo Surface Density Solution to the Dirichlet Heat Transfer Problem

T. J. Hoffman, N. E. Banks

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 205-214

March 1976

Format:

Price:$30.00

A General Method for Generating Effective Resonance Cross Sections for Heterogeneous Media

K. D. Kirby, R. A. Karam

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 215-230

March 1976

Format:

Price:$30.00

The 165Ho(n, γ) Standard Cross Section from 3 to 450 keV

R. L. Macklin

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 231-236

March 1976

Format:

Price:$30.00

Spectra of Bremsstrahlung Produced in Very Thick Lead Targets by 15-, 20-, and 25-MeV Electrons

Takashi Nakamura, Hideo Hirayama

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 237-245

March 1976

Format:

Price:$30.00

Moments Method Calculation of the Energy-Dependent Neutron Flux Due to a Point-lsotropic Fission Source in an Infinite Medium of Sodium

E. E. Morris

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 246-260

March 1976

Format:

Price:$30.00

Effect of Anisotropy in Scattering on Neutron Angular Flux Inside Slabs

Lakshmi Rangaswamy, L. S. Kothari, Feroz Ahmed

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 261-270

March 1976

Format:

Price:$30.00

Accuracy of the Quasistatic Method for Two-Dimensional Thermal Reactor Transients with Feedback

H. L. Dodds, Jr.

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 271-276

March 1976

Format:

Price:$30.00

Incorporation of Spectral Effects into One-Group Nodal Simulators

Martin Becker

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 276-278

March 1976

Format:

Price:$30.00

Anisotropic Neutron Transport Without Legendre Expansions

J. P. Odom, J. K. Shultis

Nuclear Science and Engineering / Volume 59 / Number 3 / Pages 278-281

March 1976

Format:

Price:$30.00

Remarks on “Neutron Transport with Temperature Feedback”

Aldo Belleni-Morante

Nuclear Science and Engineering / Volume 59 / Number 3 / Page 282

March 1976

Page of 3
 
 
 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement