Volume 71; Issue 2

Nuclear Science and Engineering

Volume 71; Issue 2

1

Computational Efficiency of Numerical Methods for the Multigroup, Discrete-Ordinates Neutron Transport Equations: The Slab Geometry Case

Alcouffe, R. E., Larsen, E. W., Miller, W. F., Wienke, B. R.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.40 MB

english, 1979

2

104,105,106,108,110 Pd ( n,γ ) Cross Sections Above 2.6 keV

Macklin, R. L., Halperin, J., Winters, R. R.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.55 MB

english, 1979

3

The Energy Dependence of Fission Fragment Anisotropy in Fast-Neutron-Induced Fission of Uranium-235

Ahmad, S., Islam, M. M., Khan, A. H., Khaliquzzaman, M., Husain, M., Rahman, M. A.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 413 KB

english, 1979

4

Reactivity Measurements in a Thorium Critical Assembly

Kobayashi, Keiji, Horie, Junnosuke, Kanda, Keiji, Shibata, Toshikazu

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 3.64 MB

english, 1979

5

Characteristics of a Beam-Driven Deuterium-Fueled Fusion-Fission Reactor System

Schoepf, K. F., Harms, A. A.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.05 MB

english, 1979

6

On the Eigenvalues of the Stationary and Time-Dependent Boltzmann Equation in Its Integro-Differential and Integral Forms

Protopopescu, V.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 392 KB

english, 1979

7

The Calculation of the Void Fraction by Slip Ratio Correlations: A General Method

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 777 KB

english, 1979

8

Effect of Soluble Neutron Absorbers on the Criticality of Low-Uranium-235 Enriched UO 2 Lattices

Lloyd, R. C., Durst, B. M., Clayton, E. D.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.49 MB

english, 1979

9

Discrete Transfer Cross-Section Expansion for Time-Dependent Neutron Transport

Beranek, F., Conn, R. W.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.59 MB

english, 1979

10

Factorized Kernels and the DKPL Solution to the Third Form of the Neutron Transport Equation in a Rectangular Parallelepiped

Bassini, A., Premuda, F., Wassef, W. A.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.10 MB

english, 1979

11

Thermal Radiation Properties of Interfaces Between Nuclear Reactor Materials

Chan, S. H., Tseng, H. H.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.01 MB

english, 1979

12

Analysis of Error in Monte Carlo Transport Calculations

Booth, Thomas E., Cashwell, Edmond D.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.01 MB

english, 1979

13

Multiple-Jet Thermal Mixing in a Piping Tee

Lykoudis, Paul S., Hagar, Robert C.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 1.96 MB

english, 1979

14

Accuracy and Computational Time of a Hierarchy of Growth Rate Definitions for Breeder Reactor Fuel

Maudlin, P. J., Borg, R. C., Ott, K. O.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 549 KB

english, 1979

15

6 Li( n ,α)T Cross Section from 70 to 3000 keV from the 235 U( n,f ) Calibration of a Thin Glass Scintillator

Macklin, R. L., Ingle, R. W., Halperin, J.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 565 KB

english, 1979

16

Critical Experiments with Lattices of 475-wt%- 235 U-Enriched UO 2 Rods in Water

Manaranche, J. C., Mangin, D., Maubert, L., Colomb, G., Poullot, G.

Journal:

Nuclear Science and Engineering

Year:

1979

Language:

english

File:

PDF, 3.56 MB

english, 1979