Published May 2014 | Version v1
Book Metadata-only

LEU MNSR preliminary physical design

Creators

  • 1. China Institute of Atomic Energy, Beijing (China)

Description

Low enriched uranium prototype miniature neutron source reactor (LEU MNSR) is designed on the physical with MCNP code. LEU MNSR detailed geometry structure is described in the design. According to excess reactivity requirements for LEU MNSR, 12.5% is selected for the fuel 235U enrichment. And then, minimum critical element number, thermal neutron flux density in inside irradiation seat, Central control rod efficiency, top beryllium efficiency are calculated. a suitable LEU MNSR core structure is chose. At last, using WIMSD-4, CITATION and EXTERMINATOR-2 code, Moderator temperature coefficient, Fuel reactivity coefficient, Prompt neutron lifetime and effective delayed neutron fraction are calculated. The stability characteristic of the reactor is studied with ELAP5/SCDAPSIM/MOD3.2 code. It has shown that LEU MNSR has good inherent safety. (authors)

Part of:
Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.6--computational physics sub-volume

Additional details

Publishing Information

Publisher
China Nuclear Physics Society
Imprint Place
Beijing (China)
ISBN
978-7-5022-6128-3
Imprint Title
Progress report on nuclear science and technology in China (Vol.3). Proceedings of academic annual meeting of China Nuclear Society in 2013, No.6--computational physics sub-volume
Imprint Pagination
81 p.
Journal Page Range
p. 20-24

Conference

Title
2013 academic annual meeting of China Nuclear Society
Dates
10-14 Sep 2013
Place
Harbin (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
48068539
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BERYLLIUM; CONTROL ELEMENTS; DELAYED NEUTRON FRACTION; DESIGN; ENRICHED URANIUM; ENRICHMENT; FLUX DENSITY; FUELS; GEOMETRY; IRRADIATION; LIFETIME; MNSR TYPE REACTORS; MODERATORS; PROMPT NEUTRONS; SAFETY; STABILITY; TEMPERATURE COEFFICIENT; THERMAL NEUTRONS; URANIUM 235
Descriptors DEC
ACTINIDE NUCLEI; ACTINIDES; ALKALINE EARTH METALS; ALPHA DECAY RADIOISOTOPES; BARYONS; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; FERMIONS; FISSION NEUTRONS; HADRONS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; MATERIALS; MATHEMATICS; METALS; MINUTES LIVING RADIOISOTOPES; NEUTRONS; NUCLEI; NUCLEONS; RADIOISOTOPES; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
1 fig., 7 tabs., 2 refs.