Calculation of neutron fluence in the region of the pressure vessel for the history of different reactors by using the Monte-Carlo-method-Reference-Cited by-同舟云学术

Calculation of neutron fluence in the region of the pressure vessel for the history of different reactors by using the Monte-Carlo-method

Published:1992-09 Issue:1 Volume:137 Page:71-75
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Barz H.-U.,Bertram W.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference12 articles.

1. Grundlagen der Monte-Carlo-Programme SMO und EMO zur Neutronenfluß- bzw;Barz,1985

2. SMO - Ein Monte-Carlo-Neutronenflußberechnungsprogramm;Barz;Kernenergie,1987

3. Report ZfK-705;Barz,1990

4. MCANG - Eine Bibliothek mit Gruppendaten kumulativer Winkelverteilungen für Monte-Carlo-Rechnungen;Böhmer,1984

5. K.-F. Pötter, Unpublished results, KKW Rheinsberg.

Cited by 4 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. ASYNT — An adjoint synthesis method for neutron irradiation estimation on the vessels of VVER/PWR reactors;Nuclear Engineering and Design;1997-07

2. The ASYNT Adjoint Synthesis Method for Neutron Irradiation Assessment of VVER/Pressurized Water Reactor Pressure Vessel;Nuclear Science and Engineering;1997-06

3. On “Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined by the MCNP Code”;Nuclear Science and Engineering;1996-10

4. Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence;Nuclear Technology;1996-06