Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices-Reference-Cited by-同舟云学术

Comparison among MCNP-based depletion codes applied to burnup calculations of pebble-bed HTR lattices

Published:2010-04 Issue:4 Volume:240 Page:918-924
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Bomboni E.,Cerullo N.,Fridman E.,Lomonaco G.,Shwageraus E.

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

Reference20 articles.

1. Analysis of pebble fuelled zone modeling influence on HTR core calculations;Bomboni;Nuclear Science and Engineering,2009

2. Integrated KENO Monte Carlo Transport For 3-D Depletion with SCALE;Bowman,2005

3. MCNP™—A General Monte Carlo n-Particle Transport Code;Briefmeister,2005

4. Bufalino, D., Cerullo, N., Lomonaco, G., Romanello, V., 2004. HTR-N1 Plutonium Burnup Benchmark – Results obtained by UNIPI using MONTEBURNS code.

5. Waste radiotoxicity minimization using innovative LWR-HTR-GCFR symbiotic fuel cycles;Cerullo,2005

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