Published 2013
| Version v1
Book
Transient Analysis of Generation IV quick reactors
Creators
Description
As a complement to the attached code 3D neutron-CIEMAT thermohydraulic added a module to simulate transient. Temporary kinetics is resolved by factoring flow in a spatial part and another storm. MCNP provides the reactivity and updated spatial function and COBRA-IV calculates the temperature distribution. Temporary dependence of amplitude is calculated using time delayed neutron Kinetic equations. As an example of application, examines a transient loss of flow in MYRRHA, a lead-cooled experimental reactor.
Additional details
Additional titles
- Original title (Spanish)
- Analisis de Transitorios en Reactores Rapidos de Generacion IV
Publishing Information
- Publisher
- Senda Editorial
- Imprint Place
- Reus, Tarragona (Spain)
- ISBN
- 978-84-695-9192-5
- Imprint Title
- 39 Annual Meeting of Spanish Nuclear Society, September 25-27, 2013, Reus, Tarragona (Spain)
- Imprint Pagination
- 2750 p.
- Journal Page Range
- 7 p.
Conference
- Title
- 39. Annual Meeting of Spanish Nuclear Society
- Original Conference Title
- 39. Reunion Anual Sociedad Nuclear Espanola
- Dates
- 25-27 Sep 2013
- Place
- Reus, Tarragona (Spain)
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- Spain
- INIS RN
- 45054985
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ELECTRON BEAM MELTING; ENGINEERING; MAINTENANCE; MECHANICAL ENGINEERING; NUCLEAR MEDICINE; RADIATION PROTECTION; RADIOACTIVE WASTES; RADIOLOGY; REACTOR DISMANTLING
- Descriptors DEC
- DEMOLITION; ENGINEERING; MATERIALS; MEDICINE; MELTING; NUCLEAR MEDICINE; PHASE TRANSFORMATIONS; RADIOACTIVE MATERIALS; WASTES
Optional Information
- Notes
- Imprint:39 Reunion anual Sociedad Nuclear Espanola, 25-27 Septeimbre 2013, Reus, Tarragona, Espana