Results 111 to 120 of about 3,602,304 (354)

“It Is Much Safer to Be Sparse than Connected”: Safe Control of Robotic Swarm Density Dynamics with PDE Optimization with State Constraints

Advanced Intelligent Systems, EarlyView.
This paper proposes a novel control framework to ensure safety of a robotic swarm. A feedback optimization controller is capable of driving the swarm toward a target density while keeping risk‐zone exposure below a safety threshold. Theory and experiments show how safety is more effectively achieved for sparsely connected swarms.
Longchen Niu, Gennaro Notomista
wiley   +1 more source

An automated weight window generator based on the recursive Monte-Carlo method for use in MC shielding calculations [PDF]

EPJ Web of Conferences
MCNP code provides numerous variance reduction techniques that are mainly used to optimize the analog Monte Carlo simulations. These techniques can reduce the statistical uncertainty of the simulation results while minimizing computational costs.
Yadav Pratibha, Baier Silvio, Konheiser Jörg, Rachamin Reuven   +3 more
doaj   +1 more source

Safety of Power Reactor

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1964
Safety review is made on the recent power reactor in this paper outlining about recent views of the USA and U.K. government and main safeguard devices provided for reactors in practice, together with picking up important points to be consid ered for safety.
openaire   +2 more sources

Statistical developments for target and conditional sensitivity analysis: Application on safety studies for nuclear reactor

Reliability Engineering & System Safety, 2021
A. Marrel, V. Chabridon
semanticscholar   +1 more source

A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor

, 2016
Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR).
K. Lee, K. Ha, Jae-Ho Jeong, Chiwoong Choi, Taekyeong Jeong, S. Ahn, Seung Won Lee, W. Chang, S. Kang, Jaewoon Yoo   +9 more
semanticscholar   +1 more source

Safety Experience: Reactor and Critical Facilities [PDF]

, 1955
This document provides a discussion of reactor safety of the Hanford production reactor and critical facilities.
Greager, O. H.
core   +1 more source

Simulation of Spray Injection in the Pressurizer Using RELAP5

Atom Indonesia, 2017
A modeling research using Relap5 to assess the pressurizer of a pressurized water reactor(PWR) power plant has been performed. The heater and water injection systems in the pressurizer system of the PWRare of greatimportance for system pressure control ...
S. Dibyo, S Susyadi
doaj   +1 more source

A REVIEW OF INHERENT SAFETY CHARACTERISTICS OF METAL ALLOY SODIUM-COOLED FAST REACTOR FUEL AGAINST POSTULATED ACCIDENTS

, 2015
The thermal, mechanical, and neutronic performance of the metal alloy fast reactor fuel design complements the safety advantages of the liquid metal cooling and the pool-type primary system.
T. Sofu
semanticscholar   +1 more source

FISA 2003 : EU research in reactor safety, Conclusion symposium on shared-cost and concerted actions /

, 2004
"European commission, Euratom framework programme 1998-2002, key action "Nuclear fission".""Fifth international symposium on "EU research in reactor safety" was organised in Luxembourg from 10-13 November 2003."Réf. bibliogr.
European Commission., Van Goethem, G.,, Casalta, S.,, International Symposium on "EU Research in Reactor Safety"(5th :2003 :Luxembourg), Zurita, A.,   +4 more
core  

Numerical Study on Influence of Cross Flow on Rewetting of AHWR Fuel Bundle

The Scientific World Journal, 2014
Numerical study on AHWR fuel bundle has been carried out to assess influence of circumferential and cross flow rewetting on the conduction heat transfer.
Mithilesh Kumar, D. Mukhopadhyay, A. K. Ghosh, Ravi Kumar   +3 more
doaj   +1 more source