ICRP http://www.icrp.org/index.asp International Commission on Radiological Protection en-gb Sat, 21 Jul 2018 17:20:34 +0000 Draft Report on Dose Coefficients for External Exposures to Environmental Sources Now Available for Public Consultation http://www.icrp.org/page.asp?id=391 <p><span style="font-size: 12px;">The draft&nbsp;</span><strong style="font-size: 12px;">Dose Coefficients for External Exposures to Environmental Sources</strong><span style="font-size: 12px;">&nbsp;is now available for public consultation. We welcome comments from individuals and organisations. The draft document can be downloaded from the ICRP website. Comments must be submitted through the ICRP website no later than&nbsp;</span><strong style="font-size: 12px;">October 12, 2018</strong><span style="font-size: 12px;">.&nbsp;</span><br style="font-size: 12px;" /></p> <p><span style="font-size: 12px;">Questions and inquries can be directed towards&nbsp;</span><a style="background-image: url(mailtoicon.gif); background-color: #ffffff; font-size: 12px;" href="mailto:kelsey.cloutier@icrp.org">Kelsey Cloutier</a><span style="font-size: 12px;">, Development and Communications Manager.</span></p> <h3>Abstract</h3> <p><span style="font-size: 12px;">This publication presents radionuclide-specific organ and effective dose rate coefficients for members of the public resulting from environmental external exposures to radionuclide emissions of both photons and electrons, calculated using computational phantoms representing the ICRP reference newborn, 1-year-old, 5-year-old, 10-year-old, 15- year-old, and adult males and females. Environmental radiation fields of monoenergetic photon and electron sources were firstly computed using the Monte Carlo radiation transport code PHITS (Particle and Heavy Ion Transport code System) for source geometries representing environmental radionuclide exposures including planar sources on and within the ground at different depths (representing radionuclide ground contamination from fall-out or naturally occurring terrestrial sources), volumetric sources in air (representing a radioactive cloud), and uniformly distributed sources in simulated contaminated water. For the above geometries, the exposed reference individual is considered to be completely within the radiation field. Organ equivalent dose rate coefficients for monoenergetic photons and electrons were next computed employing the PHITS code thus simulating photon and electron interactions within the tissues and organs of the exposed reference individual. For quality assurance purposes, further cross-check calculations were performed using GEANT4, EGSnrc, MCNPX, MCNP6, and the Visible Monte Carlo radiation transport codes. From the monoenergetic values, nuclide-specific effective and organ equivalent dose rate coefficients for several radionuclides for the above environmental exposures were computed using the nuclear decay data from Publication 107. The coefficients are given as dose rates normalised to radionuclide concentrations in environmental media, such as radioactivity concentration, in units of nSv h-1 Bq-1 m-2 or nSv h-1 Bq-1 m-3 and can be re-normalised to ambient dose equivalent (Sv Sv-1) or air kerma (Sv Gy-1). The findings showed that, in general, the smaller the body mass of the phantom, the higher the organ and effective dose due to (1) closer proximity to the source (in the case of ground contamination) and (2) the smaller amount of body shielding of internal organs in the younger and smaller reference phantoms. The difference in effective dose between an adult and an infant is 60-140% at a photon energy of 50 keV, while it is less than 70% above a photon energy of 100 keV, where the smaller differences are observed for air submersion and the largest differences are observed for soil contamination on the surface of the ground. For realistic exposure situations of radionuclide environmental contamination, the difference was found to be more moderate. For example, for radioactive caesium (134Cs, 136Cs, 137Cs/137mBa) deposited on and in the ground, the difference in effective dose between an adult and an infant was in the range of 20-60%, depending on the radioactivity deposition depth within the soil.&nbsp;</span><br style="font-size: 12px;" /></p> Tue, 10 Jul 2018 12:18:26 +0000 Update on Dose Coefficients for Internal Exposures to Workers and the Public http://www.icrp.org/page.asp?id=390 <p>Dose coefficients are essential to the practical implementation of the system of radiological protection. Significant progress is being made on preparing a comprehensive set of dose coefficients for occupational and public internal exposure based on <a href="publication.asp?id=ICRP%20Publication%20103">ICRP <em>Publication 103</em></a>.</p> <p>Dose coefficients rely on physical data and anatomical and biokinetic models. <em><a href="publication.asp?id=ICRP%20Publication%20107">Publication 107</a></em> provides nuclear decay data. <em><a href="publication.asp?id=ICRP%20Publication%20110">Publication 110</a></em> presents adult reference computational phantoms using voxels (three-dimensional pixels) to define organs and tissues within the body. Using these phantoms, <em><a href="publication.asp?id=ICRP%20Publication%20133">Publication 133</a></em>&nbsp;provides Specific Absorbed Fractions, an important intermediate step&nbsp;in the calculation of organ and tissue doses from radionuclides retained in body tissues.</p> <p>The Occupational Intakes of Radionuclide (OIR) series of publications presents biokinetic models, using these along with decay data and the adult voxel phantoms with their SAFs to calculate dose coefficients for occupational exposure.<em><a href="publication.asp?id=ICRP%20Publication%20130">Publication 130</a></em> (OIR part 1) describes the methodology. <em><a href="publication.asp?id=ICRP%20Publication%20134">Publication 134</a></em> (OIR part 2) and <em><a href="publication.asp?id=ICRP%20Publication%20137">Publication 137</a></em> (OIR part 3) provide dose coefficients and bioassay data for:&nbsp; H, C, P, S, Ca, Fe, Co, Zn, Sr, Y, Zr, Nb, Mo, and Tc in OIR part 2, and: Ru, Sb, Te, I, Cs, Ba, Ir, Pb, Bi, Po, Rn, Ra, Th, and U in OIR part 3.</p> <p>OIR part 4 is nearing completion, covering: La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Ac, Pa, Np, Pu, Am, Cm, Bk, Cf, Es, and Fm. OIR part 5 will cover the remaining, less commonly encountered elements and radioisotopes. This last report in the OIR series will take additional time to complete as biokinetic data are difficult to obtain.</p> <p>Dose coefficients for public exposure are also underway. These require anatomical models for adults, infants, and children, as well as the pregnant woman and embryo/fetus. These computational phantoms are complete and will be published soon, followed by a publication providing SAF values. They, and the already published adult phantoms, are already being used to compute dose coefficients for public exposure to adults, infants, and children of various ages. These will be published in two parts, one covering the elements in OIR parts 2-4, and one covering the elements in OIR part 5. The former should be published shortly after OIR part 4, while the latter, like OIR part 5, will take additional time. Dose coefficients will also be published for the embryo/fetus, and the breast-fed infant.</p> <p>For more information on dose coefficients, see the <a href="http://www.icrpaedia.org/index.php/ICRP%C3%A6dia_Guide_to_Dose_Coefficients">ICRP&aelig;dia Guide to Dose Coefficients</a>.</p> Tue, 10 Jul 2018 00:06:44 +0000 Draft Report on Radiological Protection in Therapy with Radiopharmaceuticals Now Available http://www.icrp.org/page.asp?id=387 <p><span style="font-size: 12px;">The draft&nbsp;</span><strong style="font-size: 12px;">Radiological Protection in Therapy with Radiopharmaceuticals</strong><span style="font-size: 12px;">&nbsp;is now available for public consultation. We welcome comments from individuals and organisations. The draft document can be downloaded from the <a href="page.asp?id=386">ICRP website</a>. Comments must be submitted through the ICRP website no later than&nbsp;</span><strong style="font-size: 12px;">September 21, 2018</strong><span style="font-size: 12px;">.&nbsp;</span><br style="font-size: 12px;" /></p> <p>Questions and inquries can be directed towards <a href="mailto:kelsey.cloutier@icrp.org">Kelsey Cloutier</a>, Development and Communications Manager.</p> <h3>Abstract</h3> <p><span style="font-size: 12px;">The use of radiopharmaceuticals for therapy using novel radionuclides, compounds, tracer molecules, and the administration techniques is increasing for the treatment of various tumours. The goal of radiation therapy, including therapy with radiopharmaceuticals, is to optimise the relationship between the probability of control of tumour/target tissue and complications in normal tissue. Essential to this optimisation is ability to quantify radiation dose to both tumour/target tissue and normal tissue. This report provides a framework for calculating radiation doses for various treatment approaches. In radiopharmaceutical therapy, the absorbed dose in an organ or tissue is governed by the radiopharmaceutical uptake, retention in and clearance from the various organs and tissues of the body, together with radionuclide physical half-life. These biokinetic data are based on measurements made using techniques that vary in complexity and the required accuracy will depend on the specific application. For treatment planning, absorbed dose calculations are performed prior to therapy using a trace-labelled diagnostic administration, or post-therapy on the basis of the therapy administration. Uncertainty analyses provide additional information about sources of bias and random variation and their magnitudes; these analyses show the reliability and quality of absorbed dose calculations. Effective dose can provide a measure of lifetime risk of detriment attributable to the stochastic effects of radiation exposure, principally cancer, but effective dose does not apply to short-term deterministic effects associated with radiopharmaceutical therapy. Accident prevention in radiation therapy should be an integral part of the design of facilities, equipment, and administration procedures. Optimisation of staff exposures includes consideration of equipment design, proper shielding and handling of sources, and personal protective equipment and tools, as well as education and training to promote awareness and engagement in radiation protection. The decision to hold or release a patient after radiopharmaceutical therapy should take account of estimates of possible radiation dose to members of the general public and carers from residual activity in the patient. In these situations, specific radiation protection guidance should be provided to patients and caregivers.</span></p> Thu, 14 Jun 2018 12:19:08 +0000 Former Main Commission Member Hans-Georg Menzel Delivered Prestigious Lecture http://www.icrp.org/page.asp?id=385 <p>On March 5, 2018 Former Main Commisson Member and Committee 2 Chair Hans-Georg Menzel delivered the 42nd Lauriston S. Taylor Lecture at the 2018 annual meeting of the National Council on Radiation Protection and Measurements (NCRP).</p> <p>It was the 54th annual meeting of the NCRP, held at the Hyatt Regency in Bethesda, Maryland, and his lecture was titled "Radiation Dosimetry Research for Medicine and Protection: A European Journey".&nbsp; The lecture series was founded to honour the late Dr. Lauriston S. Taylor, NCRP Founding President (1929-1977) and President Emeritus (1977-2004).</p> <p>Dr. Menzel served as Chair of Committee 2 from 2007 until 2013, and continued his role as a member of the Main Commission until 2017.&nbsp;</p> <p>More infomation on Hans, the lecture, and the meeting can be found in <a href="https://ncrponline.org/wp-content/themes/ncrp/PDFs/Press_Rel/2017/Menzel-LST.pdf">NCRP's press release</a>.</p> <p>All questions and inquiries can be directed towards <a href="mailto:kelsey.cloutier@icrp.org">Kelsey Cloutier</a>, Development and Communications Manager.</p> Mon, 11 Jun 2018 15:02:22 +0000 ICRP Welcomes New Intern: Sunny Siu http://www.icrp.org/page.asp?id=384 <p> <p>On May 8th, ICRP welcomed Sunny Siu to the Scientific Secretariat.</p> <p>The Canadian Nuclear Safety Commission (CNSC) have graciously provided support to the ICRP Scientific Secretariat team through the professional development program for students and this will be his first four-month rotation in Ottawa.</p> <p>Sunny has prior experience in the Health Physics Department at the McMaster Nuclear Reactor, Hamilton and Darlington&rsquo;s Refurbishment in Radiation Protection at Ontario Power Generation, Bowmanville.</p> <p>From the Windsor, Ontario area, Sunny has traveled throughout the province in his academic and professional career. Studying at McMaster University with a background in Health Physics and special interest in Nuclear Engineering and Reactor Physics, he has one semester left before a BSc in Medical and Health Physics.</p> <p>While at ICRP, Sunny will be assisting with the Scientific Secretariat, performing various tasks alongside the team.</p> <p>Once again, thank you to the CNSC for their partnership, collaboration, and support.</p> <p>Welcome Sunny!</p> </p> Mon, 14 May 2018 17:28:56 +0000 Summary of April 2018 Main Commission Meeting Now Available http://www.icrp.org/admin/Summary%20of%20April%202018%20Main%20Commission%20Meeting%20Quebec%20City.pdf http://www.irpa.net/admin/Summary%20of%20April%202018%20Main%20Commission%20Meeting%20Quebec%20City.pdf Fri, 11 May 2018 19:15:03 +0000 Passing of Former Main Commission Member Rudolf Mikhailovich Aleksakhin http://www.icrp.org/docs/Passing of Former Main Commission Member Rudolf Mikhailovich Aleksakhin.pdf http://www.irpa.net/docs/Passing of Former Main Commission Member Rudolf Mikhailovich Aleksakhin.pdf Wed, 9 May 2018 13:07:09 +0000 First Ever Bo Lindell Medal Awarded to Nicole E Martinez http://www.icrp.org/docs/First Ever Bo Lindell Medal Awarded to Nicole E Martinez.pdf http://www.irpa.net/docs/First Ever Bo Lindell Medal Awarded to Nicole E Martinez.pdf Mon, 7 May 2018 18:20:40 +0000 ICRP and ICRU to Celebrate Respective 90th Anniversaries in Stockholm http://www.icrp.org/docs/invitation-icrp.pdf http://www.irpa.net/docs/invitation-icrp.pdf Fri, 4 May 2018 13:40:14 +0000 Draft Report on Effective Dose Now Available for Public Consulation http://www.icrp.org/page.asp?id=383 <p><span style="font-size: 12px;">The draft report on&nbsp;</span><strong style="font-size: 12px;">The Use of Effective Dose as a Radiological Protection Quantity</strong><span style="font-size: 12px;">&nbsp;is now available for public consultation. We welcome comments from individuals and organisations. The draft document can be downloaded from the <a href="page.asp?id=382">ICRP website</a>. Comments must be submitted through the ICRP website no later than&nbsp;</span><strong style="font-size: 12px;">August 3, 2018</strong><span style="font-size: 12px;">.&nbsp;</span></p> <p><span style="font-size: 12px;">Questions and inquries can be directed towards </span><a style="font-size: 12px; background-color: #ffffff;" href="mailto:kelsey.cloutier@icrp.org">Kelsey Cloutier</a><span style="font-size: 12px;">, Development and Communications Manager.</span></p> <h3>Abstract</h3> <p><span style="font-size: 12px;">The concept of &lsquo;effective dose&rsquo; (E) was developed by ICRP as a risk-adjusted dosimetric quantity for the management of protection against stochastic effects, principally cancer, enabling comparison of planned or received doses with dose limits, dose constraints, and reference levels expressed in the same quantity. Its use allows all radiation exposures 92 from external and internal sources to be considered together and summed, relying on the assumptions of a linear-non-threshold dose-response relationship, equivalence of acute and chronic exposures at low doses or low dose rates, and equivalence of external and internal exposures. Considering exposures incurred by patients during medical procedures, E is of practical value for comparing: doses from different diagnostic examinations and interventional procedures; the use of similar technologies and procedures in different hospitals and countries; and the use of different technologies for the same medical examination, provided that the representative patients or patient populations for which the effective doses are derived are similar with regard to age and sex. As stated in the 2007 Recommendations (ICRP, 2007a), &ldquo;&hellip; risk assessment for medical diagnosis and treatment &hellip; is best evaluated using appropriate risk values for the individual tissues at risk and for the age and sex distribution of the individuals undergoing the medical procedures&rdquo;. Publication 103 (ICRP, 2007a) provides detailed explanation of the purpose and use of E and of equivalent dose to individual organs and tissues. However, questions have arisen regarding practical applications, highlighting a clear need for further guidance on specific aspects. This publication draws on the explanations provided in Publication 103 and emphasises that E has proved a valuable and robust quantity for use in the optimisation of protection, to set dose criteria and verify compliance. Conclusions are drawn that: a) Equivalent dose (H) is not required as a protection quantity. It will be more appropriate for limits for the avoidance of tissue reactions for the hands and feet, lens of the eye, and skin, to be set in terms of absorbed dose (Gy) rather than equivalent dose (Sv). b) While risk assessments for individuals based on organ/tissue doses and specific dose-risk models make best use of scientific knowledge, E may be used as an approximate indicator of possible risk, recognising that this is a pragmatic, but unintended, application of effective dose. It is made clear in this report that while doses incurred at low levels of exposure may be measured or assessed with reasonable accuracy, the associated risks are increasingly uncertain at lower doses. However, bearing in mind the uncertainties associated with risk projection to low doses, E may be considered as an approximate indicator of possible risk, with the additional consideration of variation in risk with age, sex and population group. Use of E in this way is not a substitute for risk analysis using best estimates of organ/tissue doses, appropriate information on the relative effectiveness of different radiation types, and age-, sex- and population-specific risk factors, with consideration of uncertainties.&nbsp;</span></p> Thu, 26 Apr 2018 17:48:00 +0000 ICRP Welcomes New Assistant Scientific Secretary Chunsheng Li http://www.icrp.org/page.asp?id=381 <p>Effective April 3, 2018, Dr Chunsheng Li joined Dr Hiroki Fujita as an additional Scientific Secretary at ICRP.</p> <p>Our kindest thanks to Health Canada (HC) for providing this resource.&nbsp; Dr Li joins ICRP from the Radiation Protection Bureau of HC.</p> <p>Chunsheng received his PhD in Radiochemsitry in 1998 from the Chinese Acadamey of Sciences.&nbsp; He has been working for Health Canada since 1999 as a scientiest on monitoring, dosimetry and medical management of internal radiation contamination.&nbsp; Additionally, Chunsheng has been an adjunct professor at Carleton University in Ottawa since 2010.&nbsp;</p> <p><span style="font-size: 10pt;">ICRP is fortunate to have Chunsheng's many years of experience and dedication to the field Radiolgoical Protection.&nbsp; Welcome Chunsheng!</span></p> <p><span style="font-size: 10pt;">Questions and inquiries can be directed to <a href="mailto:kelsey.cloutier@icrp,org">Kelsey Cloutier</a>, Develomepment and Comminucations Manager for ICRP.</span></p> <div></div> Mon, 9 Apr 2018 17:50:31 +0000 Passing of Former Main Commission Member Roger Berry http://www.icrp.org/docs/Passing of Former Main Commission Member Roger Berry.pdf http://www.irpa.net/docs/Passing of Former Main Commission Member Roger Berry.pdf Tue, 3 Apr 2018 19:05:51 +0000 Passing of Former Main Commission Member Julian Liniecki http://www.icrp.org/docs/Passing of Former Main Commission Member Julian Liniecki.pdf http://www.irpa.net/docs/Passing of Former Main Commission Member Julian Liniecki.pdf Mon, 26 Mar 2018 17:49:54 +0000 Publication 139, Occupational Radiological Protection in Interventional Procedures, Now Available http://www.icrp.org/page.asp?id=380 <p>Last week, Publication 139 on Occupational Radiological Protection in Interventional Procedures was released on our <a href="publication.asp?id=ICRP%20Publication%20139">website</a>.&nbsp;&nbsp;</p> <p>Questions and inquiries can be directed to <a href="mailto:kelsey.cloutier@icrp.org">Kelsey Cloutier</a>, Development and Communications Manager.</p> <p><strong style="font-size: 12px;">Abstract -</strong><span style="font-size: 12px;">&nbsp;In recent publications, such as Publications 117 and 120, the Commission provided practical advice for physicians and other healthcare personnel on measures to protect their patients and themselves during interventional procedures. These measures can only be effective if they are encompassed by a framework of radiological protection elements, and by the availability of professionals with responsibilities in radiological protection. This framework includes a radiological protection programme with a strategy for exposure monitoring, protective garments, education and training, and quality assurance of the programme implementation. Professionals with responsibilities in occupational radiological protection for interventional procedures include: medical physicists; radiological protection specialists; personnel working in dosimetry services; clinical applications support personnel from the suppliers and maintenance companies; staff engaged in training, standardisation of equipment, and procedures; staff responsible for occupational health; hospital administrators responsible for providing financial support; and professional bodies and regulators. This publication addresses these elements and these audiences, and provides advice on specific issues, such as assessment of effective dose from dosimeter readings when an apron is worn, estimation of exposure of the lens of the eye (with and without protective eyewear), extremity monitoring, selection and testing of protective garments, and auditing the interventional procedures when occupational doses are unusually high or low (the latter meaning that the dosimeter may not have been worn).</span></p> Mon, 19 Mar 2018 14:31:31 +0000 ICRP Welcomes New Assistant Scientific Secretary Hiroki Fujita http://www.icrp.org/page.asp?id=378 <p>Effective March 5, 2018, Dr Hiroki Fujita serves as one of the new Assistant Scientific Secretary's at ICRP.</p> <p>For the first time, the Assistant Scientific Secretary is from the Japanese Atomic Energy Agency (JAEA), and will last for a term of three years.&nbsp; We're excited about this new relationship with JAEA, and must thank CRIEPI Radiation Research Safety Center, who gracioulsy supported this role over a six year span, through three quality experts in two-year intervals.</p> <p>Hiroki received his Doctorate in Science from the University of Niigata, and comes to ICRP from the Radiation Protection Department, Nuclear Fuel Cycle Engineering Laboratories, Sector of Decomissioning and Radioactive Waste Management at JAEA.</p> <p>For the next few weeks, Hiroki will be training alongside current Assistant Scientific Secretary Haruyuki Ogino, who will return to Japan in the next few weeks.&nbsp; Haru has been an integral part of the ICRP family these last few years, and he will be surely missed.&nbsp; Our sincerest gratitude and thanks to Haru, and welcome Hiroki.</p> Wed, 7 Mar 2018 19:56:56 +0000 Publication 138, Ethical Foundations of the System of Radiological Protection, Now Available http://www.icrp.org/page.asp?id=377 <p>Last week, Publication 138 was published on our <a href="publication.asp?id=ICRP%20Publication%20138">website</a>, ending the long awaited release of Ethical Foundations of the System of Radiological Protection.</p> <p>Questions can be directed to <a href="mailto:kelsey.cloutier@icrp.org">Kelsey Cloutier</a>, Development and Communications Manager.</p> <p><strong>Abstract</strong> -&nbsp;Despite a longstanding recognition that radiological protection is not only a matter of science, but also ethics, ICRP publications have rarely addressed the ethical foundations of the system of radiological protection explicitly. The purpose of this publication is to describe how the Commission has relied on ethical values, either intentionally or indirectly, in developing the system of radiological protection with the objective of presenting a coherent view of how ethics is part of this system. In so doing, it helps to clarify the inherent value judgements made in achieving the aim of the radiological protection system as underlined by the Commission in Publication 103. Although primarily addressed to the radiological protection community, this publication is also intended to address authorities, operators, workers, medical professionals, patients, the public, and its representatives (e.g. NGOs) acting in the interest of the protection of people and the environment. This publication provides the key steps concerning the scientific, ethical, and practical evolutions of the system of radiological protection since the first ICRP publication in 1928. It then describes the four core ethical values underpinning the present system: beneficence/non-maleficence, prudence, justice, and dignity. It also discusses how these core ethical values relate to the principles of radiological protection, namely justification, optimisation, and limitation. The publication finally addresses key procedural values that are required for the practical implementation of the system, focusing on accountability, transparency, and inclusiveness. The Commission sees this publication as a founding document to be elaborated further in different situations and circumstances.<br style="font-size: 12px;" /></p> Mon, 26 Feb 2018 15:10:43 +0000 Highly Anticipated Dose Coefficients for Radon Now Available on newly Launched ICRPaedia.org http://www.icrp.org/page.asp?id=375 <p class="MsoNormal"><span style="font-size: 10pt;">Radon, a naturally occurring gas that is found everywhere, is the largest contributor to radiation dose from natural sources world-wide, and the second leading cause of lung cancer after smoking.</span></p> <p class="MsoNormal"><span style="font-size: 10pt;">Given this, it is not surprising that radon has long been an important subject for radiological protection. A new </span><a style="background-color: #ffffff; font-size: 10pt;" href="http://www.icrpaedia.org/images/f/fd/ICRPRadonSummary.pdf">Summary of ICRP Recommendations on Radon</a><span style="font-size: 10pt;"> traces ICRP efforts on radon from </span><a style="font-size: 10pt;" href="publication.asp?id=ICRP%20Publication%2024">Publication 24</a><span style="font-size: 10pt;"> (1977) to </span><a style="font-size: 10pt;" href="publication.asp?id=ICRP%20Publication%20137">Publication 137, Occupational Intakes of Radionuclides: Part 3</a><span style="font-size: 10pt;"> (OIR 3), released earlier this week.</span></p> <p class="MsoNormal">OIR 3 provides dose coefficients for radon and radon progeny:</p> <p class="MsoNormal">&ldquo;For &hellip; inhalation of radon and radon progeny in underground mines and in buildings, in most circumstances, the Commission recommends a dose coefficient of 3 mSv per mJ h m<sup>-3</sup> (approximately 10 mSv WLM<sup>-1</sup>) &hellip; However, for indoor workplaces where workers are engaged in substantial physical activities, and for workers in tourist caves, the Commission recommends a dose coefficient of 6 mSv per mJ h m<sup>-3</sup> (approximately 20 mSv WLM<sup>-1</sup>)&rdquo;</p> <p class="MsoNormal">Considerably more information is available in OIR 3 and the Summary of Recommendations referred to above.</p> <p class="MsoNormal">In the coming weeks, radon will be highlighted on <a href="http://www.icrpaedia.org/index.php?title=Main_Page">ICRPaedia</a>, creating a central location where interested organisations, professionals, and members of the public can find an easy-to-understand summary of ICRP recommendations on radon.</p> <p class="MsoNormal"><span style="font-size: 10pt;">General inquiries may be directed to </span><span style="font-size: 10pt; text-decoration: underline;"><a href="mailto:kelsey.cloutier@icrp.org">Kelsey Cloutier</a></span><span style="font-size: 10pt;">, ICRP Development and Communications Manager.</span></p> Fri, 2 Feb 2018 15:37:03 +0000 Publication 137, Occupational Intakes of Radionuclides Part 3, Now Available http://www.icrp.org/page.asp?id=374 <p class="MsoNormal"><span style="font-size: 10pt;">The next installment in the series of Occupational Intakes of Radionuclides (OIR) reports is now published.</span></p> <p class="MsoNormal"><span style="font-size: 10pt;">The OIR series provides committed effective dose per intake (Sv Bq</span><sup>-1</sup><span style="font-size: 10pt;"> intake) for inhalation and ingestion, committed effective dose per content (Sv Bq</span><sup>-1</sup><span style="font-size: 10pt;"> measurement) for inhalation, and graphs of retention and excretion data per Bq intake for inhalation. An electronic annex contains a comprehensive set of committed effective and equivalent dose coefficients, committed effective dose per content functions, and reference bioassay functions.</span></p> <p class="MsoNormal"><span style="text-decoration: underline;"><a href="publication.asp?id=ICRP%20Publication%20130">OIR 1 (Publication 130)</a></span> describes the assessment of internal occupational exposure to radionuclides, biokinetic and dosimetric models, methods of individual and workplace monitoring, and general aspects of retrospective dose assessment.</p> <p class="MsoNormal"><span style="text-decoration: underline;"><a href="publication.asp?id=ICRP%20Publication%20134">OIR 2 (Publication 134)</a></span> provides data on radionuclides of: hydrogen (H), carbon (C), phosphorus (P), sulphur (S), calcium (Ca), iron (Fe), cobalt (Co), zinc (Zn), strontium (Sr), yttrium(Y), zirconium (Zr), niobium (Nb), molybdenum (Mo), and technetium (Tc).</p> <p class="MsoNormal"><span style="text-decoration: underline;"><a href="publication.asp?id=ICRP%20Publication%20137">OIR 3 (Publication 137)</a></span> provides data on radionuclides of: ruthenium (Ru), antimony (Sb), tellurium (Te), iodine (I), caesium (Cs), barium (Ba), iridium (Ir), lead (Pb), bismuth (Bi), polonium (Po), radon (Rn), radium (Ra), thorium (Th), and uranium (U).</p> <p><a style="font-size: 10pt;"><span style="font-size: 11.0pt; line-height: 107%;">General inquiries may be directed to&nbsp;</span></a><a style="font-size: 10pt;" href="mailto:kelsey.cloutier@icrp.org"><span style="font-size: 11.0pt; line-height: 107%;">Kelsey Cloutier,</span></a><a style="font-size: 10pt;"><span style="font-size: 11pt; line-height: 107%;"><span style="font-family: Calibri, sans-serif;">&nbsp;I</span></span></a><a style="font-size: 10pt;"><span style="font-size: 11pt; line-height: 107%;"><span style="font-family: Calibri, sans-serif;">CRP Development and Communications Manager.</span></span></a></p> Tue, 30 Jan 2018 14:45:30 +0000 Summary of October 2017 C2 Meeting in Paris http://www.icrp.org/docs/Summary of October 2017 C2 Meeting Paris.pdf http://www.irpa.net/docs/Summary of October 2017 C2 Meeting Paris.pdf Fri, 19 Jan 2018 19:28:49 +0000 Summary of October 2017 C3 Meeting in Paris http://www.icrp.org/docs/Summary of October 2017 C3 Meeting Paris .pdf http://www.irpa.net/docs/Summary of October 2017 C3 Meeting Paris .pdf Tue, 19 Dec 2017 13:59:03 +0000