Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term Indian DEMO fusion reactor
Published 2020 View Full Article
- Home
- Publications
- Publication Search
- Publication Details
Title
Helium cooled dual breeder blanket–preliminary design analyses of a candidate breeding blanket concept for near term Indian
DEMO
fusion reactor
Authors
Keywords
-
Journal
INTERNATIONAL JOURNAL OF ENERGY RESEARCH
Volume -, Issue -, Pages -
Publisher
Wiley
Online
2020-05-29
DOI
10.1002/er.5555
References
Ask authors/readers for more resources
Related references
Note: Only part of the references are listed.- One-dimensional nuclear design analyses of the SST-2
- (2019) Chandan Danani et al. PRAMANA-JOURNAL OF PHYSICS
- A neutronic experiment to support the design of Indian TBM shield module for ITER
- (2019) H L Swami et al. PLASMA SCIENCE & TECHNOLOGY
- Activation characteristics of candidate structural materials for a near-term Indian fusion reactor and the impact of their impurities on design considerations
- (2018) H L SWAMI et al. PLASMA SCIENCE & TECHNOLOGY
- Design optimization of first wall and breeder unit module size for the Indian HCCB blanket module
- (2018) Deepak SHARMA et al. PLASMA SCIENCE & TECHNOLOGY
- Fusion Neutrons: Tritium Breeding and Impact on Wall Materials and Components of Diagnostic Systems
- (2018) Marek Rubel JOURNAL OF FUSION ENERGY
- Design and analysis of SST-2 fusion reactor
- (2016) R. Srinivasan FUSION ENGINEERING AND DESIGN
- Neutronic performance issues of the breeding blanket options for the European DEMO fusion power plant
- (2016) U. Fischer et al. FUSION ENGINEERING AND DESIGN
- Neutronic performance of Indian LLCB TBM set conceptual design in ITER
- (2016) H.L. Swami et al. FUSION ENGINEERING AND DESIGN
- Progress of R&D on water cooled ceramic breeder for ITER test blanket system and DEMO
- (2016) Yoshinori Kawamura et al. FUSION ENGINEERING AND DESIGN
- Neutronics Analysis of Water-Cooled Ceramic Breeder Blanket for CFETR
- (2016) Qingjun Zhu et al. PLASMA SCIENCE & TECHNOLOGY
- Neutronics requirements for a DEMO fusion power plant
- (2015) U. Fischer et al. FUSION ENGINEERING AND DESIGN
- Blanket/first wall challenges and required R&D on the pathway to DEMO
- (2015) Mohamed Abdou et al. FUSION ENGINEERING AND DESIGN
- Overview of design and thermal–hydraulic analysis of Indian solid breeder blanket concept
- (2013) Paritosh Chaudhuri et al. FUSION ENGINEERING AND DESIGN
- Overview of Helium Cooled Ceramic Reflector Test Blanket Module development in Korea
- (2013) Seungyon Cho et al. FUSION ENGINEERING AND DESIGN
- Fusion research programme in India
- (2013) SHISHIR DESHPANDE et al. SADHANA-ACADEMY PROCEEDINGS IN ENGINEERING SCIENCES
- Overview of the ITER TBM Program
- (2012) L.M. Giancarli et al. FUSION ENGINEERING AND DESIGN
- MHD thermofluid issues of liquid-metal blankets: Phenomena and advances
- (2010) Sergey Smolentsev et al. FUSION ENGINEERING AND DESIGN
- Thermal–hydraulic and thermo-structural analysis of first wall for Indian DEMO blanket module
- (2009) Paritosh Chaudhuri et al. FUSION ENGINEERING AND DESIGN
- Plasma–surface interaction issues of an all-metal ITER
- (2009) J.N. Brooks et al. NUCLEAR FUSION
- Strategy for the Indian DEMO design
- (2008) R. Srinivasan et al. FUSION ENGINEERING AND DESIGN
Add your recorded webinar
Do you already have a recorded webinar? Grow your audience and get more views by easily listing your recording on Peeref.
Upload NowBecome a Peeref-certified reviewer
The Peeref Institute provides free reviewer training that teaches the core competencies of the academic peer review process.
Get Started