Published 2019
| Version v1
Book
The constructing status and preliminary evaluation for the criticality safety design of Okuma Analysis and Research Center
Creators
- 1. Japan Atomic Energy Agency, Fukushima 970-8026 (Japan)
Description
As a result of preliminary criticality safety evaluation, it was cleared that using pure MOX fuel as the fuel debris is the most conservative on the criticality safety evaluation. From the result of evaluation, it was shown that 5 kg fuel debris are safely handled in Laboratory-2. As the future work, the feasibility of criticality safety control method in consideration of the analysis operations of the fuel debris in Laboratory-2 will be confirmed
Additional details
Publishing Information
- Publisher
- Indira Gandhi Centre for Atomic Research
- Imprint Place
- Kalpakkam (India)
- ISBN
- 978-81-933477-3-7
- Imprint Title
- Proceedings of the fifty sixth annual meeting on hot laboratories and remote handling: book of abstracts
- Imprint Pagination
- 322 p.
- Journal Page Range
- p. 30-31
Conference
- Title
- 56. annual meeting on hot laboratories and remote handling
- Acronym
- HOTLAB-2019
- Dates
- 8-12 Sep 2019
- Place
- Mamallapuram (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 51095605
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; FUEL CYCLE; FUEL CYCLE CENTERS; GLOVEBOXES; MIXED OXIDE FUELS; RADIATION PROTECTION; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- ENERGY SOURCES; EQUIPMENT; FUELS; LABORATORY EQUIPMENT; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; REACTOR MATERIALS; SOLID FUELS