Comparison of measured and calculated neutron transmission through steel for a 252Cf source-Reference-Cited by-同舟云学术

Comparison of measured and calculated neutron transmission through steel for a 252Cf source

Published:1993-09 Issue:9 Volume:20 Page:585-604
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Sajo E.,Williams M.L.,Asgari M.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference8 articles.

1. ENDF/B summary documentation;Garber,1975

2. SCALE: A modular code system for performing standardized computer analyses for licensing evaluation, Sect. F1;Greene;Report NUREG/CR-0200 (ORNL/NUREG/CSD-2/R4),1990

3. ENDF/B summary documentation,1979

4. Application of the LEPRICON Unfolding Procedure to the Arkansas Nuclear One-Unit 1 Reactor

5. SCALE: a modular code system for performing standardized computer analyses for licensing evaluation, Sect. F3;Petrie;Report NUREG/CR-0200 (ORNL/NUREG/CSD-2/R4),1990

Cited by 15 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Development of HELIOS/BIPR/PARCS/MCNP6 Computation Route for WWER RPV Neutron Fluence Analysis and Validation Against Ex-Vessel Detector Measurement Data;Nuclear Science and Engineering;2023-12-19

2. Neutronics Calculations to Support the Fusion Evaluated Nuclear Data Library (FENDL);Fusion Science and Technology;2021-08-18

3. Performance of ENDF/B-VIII.0 library for VVER reactors criticality safety, fuel depletion and reactor dosimetry applications;Annals of Nuclear Energy;2020-12

4. Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems;Nuclear Technology;2019-07-01

5. Investigation of Neutron Cross Section for Iron in the ENDF Library with Pulsed Sphere Measurements;Nuclear Science and Engineering;2019-05-06