ANS / Publications / Journals / Nuclear Science and Engineering

A Global Physics Approach to Transmutation of Radioactive Nuclei

M. Salvatores, I. Slessarev, M. Uematsu

Nuclear Science and Engineering / Volume 116 / Number 1 / January 1994 / Pages 1-18

Technical Paper / dx.doi.org/10.13182/NSE94-A21476

Measurement of Radioactivity Production for ⁴⁸V ⁵⁶Co, and ⁶⁵Zn Via the (p,n) Sequential Reaction Processes in Titanium, Iron, and Copper Metals Associated with 14-MeV Neutron Irradiation

Y. Ikeda, C. Konno, H. Maekawa

Nuclear Science and Engineering / Volume 116 / Number 1 / January 1994 / Pages 19-27

Technical Paper / dx.doi.org/10.13182/NSE94-A21477

Measurement of Neutron Activation Cross Sections for the ⁹⁹Tc(n,p)⁹⁹Mo, ⁹⁹Tc(n,α)⁹⁶Nb, ⁹⁹Tc(n,n′α)⁹⁵Nb, and“Tc(n,n′)^99mTc Reactions at 13.5 and 14.8 MeV

Y. Ikeda, E. T. Cheng, C. Konno, H. Maekawa

Nuclear Science and Engineering / Volume 116 / Number 1 / January 1994 / Pages 28-34

Technical Paper / dx.doi.org/10.13182/NSE94-A21478

A Method for Calculating Double-Differential Cross Sections of Alpha-Particle Emissions

Jingshang Zhang

Nuclear Science and Engineering / Volume 116 / Number 1 / January 1994 / Pages 35-41

Technical Paper / dx.doi.org/10.13182/NSE93-28

Solution of the Mathematical Adjoint Equations for an Interface Current Nodal Formulation

W. S. Yang, T. A. Taiwo, H. Khalil

Nuclear Science and Engineering / Volume 116 / Number 1 / January 1994 / Pages 42-54

Technical Paper / dx.doi.org/10.13182/NSE94-A21480

An Investigation of the Temporal Subdomain Method for Solving the Finite Element Formulation of the Space-Time Reactor Kinetics Equations

Haluk Utku, John M. Christenson

Nuclear Science and Engineering / Volume 116 / Number 1 / January 1994 / Pages 55-66

Technical Note / dx.doi.org/10.13182/NSE94-A21481

The Reactor Noise Threshold

Gregory D. Spriggs

Nuclear Science and Engineering / Volume 116 / Number 1 / January 1994 / Pages 67-72

Technical Note / dx.doi.org/10.13182/NSE94-A21482

A Fission-Source Acceleration Technique for Time-Dependent Even-Parity S_n Calculations

J. E. Morel, J. M. McGhee

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 73-85

Technical Paper / dx.doi.org/10.13182/NSE94-A21484

Effective Diffusion Homogenization of Cross Sections for Pressurized Water Reactor Core Calculations

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 86-95

Technical Paper / dx.doi.org/10.13182/NSE94-A21485

A Probabilistic Method for Evaluating Reactivity Feedbacks and Its Application to Experimental Breeder Reactor II

R. W. Schaefer

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 96-112

Technical Paper / dx.doi.org/10.13182/NSE94-A21486

A Monte Carlo Variance Reduction Approach for Non-Boltzmann Tallies

Thomas E. Booth

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 113-124

Technical Paper / dx.doi.org/10.13182/NSE94-A21487

Excitation Functions of Neutron Threshold Reactions on Some Isotopes of Germanium, Arsenic, and Selenium in the 6.3- to 14.7-MeV Energy Range

I. Birn, S. M. Qaim

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 125-137

Technical Paper / dx.doi.org/10.13182/NSE94-A21488

Measurements of the Modified Conversion Ratio by Gamma-Ray Spectrometry of Fuel Rods for Water-Moderated UO₂ Cores

Ken Nakajima, Masanori Akai, Takenori Suzaki

Nuclear Science and Engineering / Volume 116 / Number 2 / February 1994 / Pages 138-146

Technical Paper / dx.doi.org/10.13182/NSE94-A21489

Vectorization Methods Development for a New Version of the KENO-V.a Criticality Safety Code

D. F. Hollenbach, L. M. Petri, H. L. Dodds

Nuclear Science and Engineering / Volume 116 / Number 3 / March 1994 / Pages 147-164

Technical Paper / dx.doi.org/10.13182/NSE94-A19810

A New Approach of Analytic Basis Function Expansion to Neutron Diffusion Nodal Calculation

Jae Man Noh, Nam Zin Cho

Nuclear Science and Engineering / Volume 116 / Number 3 / March 1994 / Pages 165-180

Technical Paper / dx.doi.org/10.13182/NSE94-A19811

Fast Shutdown Margin Calculation Using Perturbation Theory with Regionwise Flux Expansion

Jeng-Ming Fang, Yen-Wan H. Liu, Horng-Kuang Liu, Pin-Wu Kao, Jing-Tong Yang

Nuclear Science and Engineering / Volume 116 / Number 3 / March 1994 / Pages 181-204

Technical Paper / dx.doi.org/10.13182/NSE94-A19812

A Study on Applicability of Decay Ratio Estimation in a Pressurized Water Reactor

G. Por, J. Runkel

Nuclear Science and Engineering / Volume 116 / Number 3 / March 1994 / Pages 205-212

Technical Paper / dx.doi.org/10.13182/NSE94-A19813

Statistical Model Calculation of the ²³⁷U Fission Cross Section

J. P. Lestone, A. Gavron

Nuclear Science and Engineering / Volume 116 / Number 3 / March 1994 / Pages 213-217

Technical Paper / dx.doi.org/10.13182/NSE94-A19814

Study of Photon Attenuation Coefficients of Some Multielement Materials

G. S. Bhandal, K. Singh

Nuclear Science and Engineering / Volume 116 / Number 3 / March 1994 / Pages 218-222

Technical Note / dx.doi.org/10.13182/NSE94-A19815

Stability, Accuracy, and Convergence of the Numerical Methods in RELAP5/MOD3

A. S.-L. Shieh, R. Krishnamurthy, V. H. Ransom

Nuclear Science and Engineering / Volume 116 / Number 4 / April 1994 / Pages 227-244

Technical Paper / dx.doi.org/10.13182/NSE94-A18984

Rod Bundle Thermal-Hydraulic and Melt Progression Analysis of CORA Severe Fuel Damage Experiments

Kune Y. Suh

Nuclear Science and Engineering / Volume 116 / Number 4 / April 1994 / Pages 245-268

Technical Paper / dx.doi.org/10.13182/NSE94-A18985

Comparison of Scientific Computing Platforms for MCNP4A Monte Carlo Calculations

J. S. Hendricks, R. C. Brockhoff

Nuclear Science and Engineering / Volume 116 / Number 4 / April 1994 / Pages 269-277

Technical Paper / dx.doi.org/10.13182/NSE94-A18986

Neutron Penetration Through Iron and Concrete Shields with the Use of 22.0- and 32.5-MeV Quasi-Monoenergetic Sources

Toshio Ishikawa

Nuclear Science and Engineering / Volume 116 / Number 4 / April 1994 / Pages 278-290

Technical Paper / dx.doi.org/10.13182/NSE94-A18987

Space Proton Transport in One Dimension

Stanley L. Lamkin and Govind S. Khandelwal, Judy L. Shinn, John W. Wilson

Nuclear Science and Engineering / Volume 116 / Number 4 / April 1994 / Pages 291-299

Technical Paper / dx.doi.org/10.13182/NSE94-A18988

A New Approach to Core-Reflector Boundary Conditions for Nodal Reactor Computations

Hyung Kook Joo, Chang Hyo Kim, Jae Man Noh, Si-Hwan Kim

Nuclear Science and Engineering / Volume 116 / Number 4 / April 1994 / Pages 300-312

Technical Paper / dx.doi.org/10.13182/NSE94-A18989

Detecting Faults in a Nuclear Power Plant by Using Dynamic Node Architecture Artificial Neural Networks

Anujit Basu, Eric B. Bartlett

Nuclear Science and Engineering / Volume 116 / Number 4 / April 1994 / Pages 313-325

Technical Paper / dx.doi.org/10.13182/NSE94-A18990