Published 2010 | Version v1
Miscellaneous Open

Criticality safety calculation for proposed conceptual design of RTP spent fuel pool

Creators

  • 1. Malaysian Nuclear Agency, Bangi, Kajang, Selangor (Malaysia), Nuclear Power Div.

Description

The estimated value of the criticality, keff for the design of the proposed fuel storage pool used for RTP was carried out using Monte Carlo, MCNP. This study aims to get the very best way to ensure the collection of used fuel is not reaching the value of keff, 0.8. Fuel type 20 w / o % was modeled in detail in order 7x7 shelf in the pond water. The calculation has been done several times to obtain the relationship between the distances of each fuel assembly with the keff value. Based on several sets of calculations, it appears that the criticality values decreased exponentially with increasing distance between the fuels. It is hoped that this study will assist in the provision of fuel storage design for RTP. (author)

Availability note (English)

Also available in Malaysian Nuclear Agency Document Delivery Center by email: mohdhafizal@nuclearmalaysia.gov.my

Files

43056437.pdf

Files (317.4 kB)

Name Size Download all
md5:824e7e86b0387bd1e928e52e63716600
317.4 kB Preview Download

Additional details

Additional titles

Original title (English)
Pengiraan keselamatan kritikaliti untuk cadangan rekaan kolam penyimpanan bahan api terpakai RTP

Publishing Information

Imprint Pagination
9 p.
Report number
INIS-MY--2012-075

Conference

Title
Research and Development Seminar 2010
Acronym
RnD Seminar 2010
Dates
12-15 Oct 2010
Place
Bangi (Malaysia)

INIS

Country of Publication
Malaysia
Country of Input or Organization
Malaysia
INIS RN
43056437
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRITICALITY; DESIGN; FUEL ASSEMBLIES; FUEL STORAGE POOLS; MONTE CARLO METHOD; REACTOR SAFETY; RESEARCH REACTORS; RTP REACTOR; SPENT FUELS
Descriptors DEC
CALCULATION METHODS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Poster presentation. 5 figs.